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Sample records for e3640 decommissioning aberdeen

  1. Evaluation of decommissioning alternatives for the Pilot Plant Complex, Aberdeen Proving Ground

    Energy Technology Data Exchange (ETDEWEB)

    Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report presents an evaluation of four decommissioning alternatives for the Pilot Plant Complex (PPC), an inactive chemical weapons research, development, and production facility consisting of nine buildings located in the Edgewood Area of the Aberdeen Proving Ground in Maryland. Decommissioning the PPC involves six steps: (1) assessing existing conditions; (2) dismantling the aboveground portions of the buildings (including the floor slabs, paved roads, and sidewalks within the PPC); (3) reducing the size of the demolition debris and sealing the debris in containers for later testing and evaluation; (4) testing and evaluating the debris; (5) conducting site operation and maintenance activities; and (6) recycling or disposing of the debris with or without prior treatment, as appropriate.

  2. Preliminary assessment of risk from toxic materials that might be mobilized in the decommissioning of Aberdeen Proving Ground Building E5032

    Energy Technology Data Exchange (ETDEWEB)

    Rosenblatt, D.H.; Brubaker, K.L.

    1991-12-01

    Aberdeen Proving Ground Building E5032 is scheduled for decommissioning, that is, for demolition. Because the building was formerly used for small-scale operations with incendiary and toxic chemical agents, it presents unusual concerns for occupational and public health safety during the demolition. For this reason, an anticipatory risk assessment was conducted, taking into consideration the building`s history, properties of potential residual contaminants (particularly chemical and incendiary agents), and assumptions relating to meteorological conditions and envisioned modes of demolition. Safe maximum levels in concrete floors for the worst case were estimated to be: white phosphorus, 3200 mg/kg; mustard, 94 mg/kg; nerve agent GA (tabun), 6 mg/kg; cyanide, 500 mg/kg; and sulfide, 1400 mg/kg. These values will serve as planning guidance for the activities to follow. It is emphasized that the estimates must be reviewed, and perhaps revised, after sampling and analysis are completed, the demolition methodology is chosen, and dust emissions are measured under operating conditions.

  3. Preliminary assessment of risk from toxic materials that might be mobilized in the decommissioning of Aberdeen Proving Ground Building E5032

    Energy Technology Data Exchange (ETDEWEB)

    Rosenblatt, D.H.; Brubaker, K.L.

    1991-12-01

    Aberdeen Proving Ground Building E5032 is scheduled for decommissioning, that is, for demolition. Because the building was formerly used for small-scale operations with incendiary and toxic chemical agents, it presents unusual concerns for occupational and public health safety during the demolition. For this reason, an anticipatory risk assessment was conducted, taking into consideration the building's history, properties of potential residual contaminants (particularly chemical and incendiary agents), and assumptions relating to meteorological conditions and envisioned modes of demolition. Safe maximum levels in concrete floors for the worst case were estimated to be: white phosphorus, 3200 mg/kg; mustard, 94 mg/kg; nerve agent GA (tabun), 6 mg/kg; cyanide, 500 mg/kg; and sulfide, 1400 mg/kg. These values will serve as planning guidance for the activities to follow. It is emphasized that the estimates must be reviewed, and perhaps revised, after sampling and analysis are completed, the demolition methodology is chosen, and dust emissions are measured under operating conditions.

  4. Decommissioning Handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  5. Decommissioning handbook

    Energy Technology Data Exchange (ETDEWEB)

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  6. About decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brosche, Dieter [Bayernwerk AG, Muenchen (Germany); Klein, K. [Badenwerk AG, Kalrsruhe (Germany); Vollradt, Juergen [Vereinigte Elektrizitaetswerke Westfalen AG, Dortmund (Germany)

    2015-10-15

    The IAEA organised an International Symposium in 1978, which dealt with the main aspects of decommissioning nuclear plants. Sufficient practical experiences and elaborated decommissioning concepts and techniques are already available. Unsolvable problems or only solvable with tremendous efforts of time and expenses are according to the opinion of experts not to be expected. Important statements concern above all the dose load of the decommissioning staff and the costs for decommissioning.

  7. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  8. Site decommissioning management plan

    Energy Technology Data Exchange (ETDEWEB)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  9. Lessons Learned for Decommissioning Planning

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Wook; Kim, Young-gook; Kim, Hee-keun [Korea Hydro and Nuclear Power Co. LTD, Daejeon (Korea, Republic of)

    2015-10-15

    The purpose of this paper is to introduce the U.S. nuclear industrial's some key lessons learned especially for decommissioning planning based on which well informed decommissioning planning can be carried out. For a successful decommissioning, it is crucial to carry out a well-organized decommissioning planning before the decommissioning starts. This paper discussed four key factors which should be decided or considered carefully during the decommissioning planning period with introduction of related decommissioning lessons learned of U.S. nuclear industry. Those factors which have been discussed in this paper include the end state of a site, the overall decommissioning strategy, the management of the spent fuels, and the spent fuel pool island. Among them, the end state of a site should be decided first as it directs the whole decommissioning processes. Then, decisions on the overall decommissioning strategy (DECON vs. SAFSTOR) and the management of the spent fuels (wet vs. dry) should follow. Finally, the spent fuel pool island should be given due consideration because its implementation will result in much cost saving. Hopefully, the results of this paper would provide useful inputs to performing the decommissioning planing for the Kori unit 1.

  10. Particle-accelerator decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Opelka, J.H.; Mundis, R.L.; Marmer, G.J.; Peterson, J.M.; Siskind, B.; Kikta, M.J.

    1979-12-01

    Generic considerations involved in decommissioning particle accelerators are examined. There are presently several hundred accelerators operating in the United States that can produce material containing nonnegligible residual radioactivity. Residual radioactivity after final shutdown is generally short-lived induced activity and is localized in hot spots around the beam line. The decommissioning options addressed are mothballing, entombment, dismantlement with interim storage, and dismantlement with disposal. The recycle of components or entire accelerators following dismantlement is a definite possibility and has occurred in the past. Accelerator components can be recycled either immediately at accelerator shutdown or following a period of storage, depending on the nature of induced activation. Considerations of cost, radioactive waste, and radiological health are presented for four prototypic accelerators. Prototypes considered range from small accelerators having minimal amounts of radioactive mmaterial to a very large accelerator having massive components containing nonnegligible amounts of induced activation. Archival information on past decommissionings is presented, and recommendations concerning regulations and accelerator design that will aid in the decommissioning of an accelerator are given.

  11. Aberdeen City Garden: Beyond Landscape or Architecture

    NARCIS (Netherlands)

    Jauslin, D.

    2012-01-01

    A team around the New York based Architects Diller, Scofidio & Renfro DS+R won a competition for the Aberdeen City Garden in January 2012 together with OLIN and Keppie Design. The proposal supported by a private deed to the city passed a public referendum in the Scottish costal town in March 2012 af

  12. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  13. Workshop on decommissioning; Seminarium om avveckling

    Energy Technology Data Exchange (ETDEWEB)

    Broden, K. (ed.)

    2005-12-15

    A Nordic workshop on decommissioning of nuclear facilities was held at Risoe in Denmark September 13-15, 2005. The workshop was arranged by NKS in cooperation with the company Danish Decommissioning, DD, responsible for decommissioning of nuclear facilities at Risoe. Oral presentations were made within the following areas: International and national recommendations and requirements concerning decommissioning of nuclear facilities Authority experiences of decommissioning cases Decommissioning of nuclear facilities in Denmark Decommissioning of nuclear facilities in Sweden Plans for decommissioning of nuclear facilities in Norway Plans for decommissioning of nuclear facilities in Finland Decommissioning of nuclear facilities in German and the UK Decommissioning of nuclear facilities in the former Soviet Union Results from research and development A list with proposals for future work within NKS has been prepared based on results from group-work and discussions. The list contains strategic, economical and political issues, technical issues and issues regarding competence and communication. (au)

  14. 76 FR 35511 - Decommissioning Planning

    Science.gov (United States)

    2011-06-17

    ... Planning; Final Rule #0;#0;Federal Register / Vol. 76 , No. 117 / Friday, June 17, 2011 / Rules and... Decommissioning Planning AGENCY: Nuclear Regulatory Commission. ACTION: Final rule. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is amending its regulations to improve decommissioning...

  15. Interim progress report addendun - environmental geophysics: Building E5032 decommissioning, Aberdeen Proving Ground, January 1994 resurvey

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, M.D.; McGinnis, L.D.; Benson, M.A.; Borden, H.M.; Padar, C.A.

    1994-12-01

    Geophysical surveying around Building E5032 using three new continuously recording geophysical instruments - two types of electromagnetic induction instruments and a cesium vapor magnetometer that were unavailable at the time of the original survey - has provided additional information for defining the location of buried debris, vaults, tanks, and the drainage/sump system near the building. The dominant geophysical signature around Building E5032 consists of a complex pattern of linear magnetic, electrical-conductivity, and electromagnetic field anomalies that appear to be associated with drainage/sewer systems, ditches, past railway activity, the location for Building T5033 (old number 99A), and the probable location of Building 91. Integrated analysis of data acquired using the three techniques, plus a review of the existing ground-penetrating-radar data, allow a more thorough definition of the sources for the observed anomalies.

  16. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.

  17. Decontamination & decommissioning focus area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  18. Power Plant decommissioning

    Directory of Open Access Journals (Sweden)

    Mažeika Jonas

    2014-11-01

    Full Text Available On a first attempt, the determination of 14C and 36Cl activity concentrations in basic operational waste (spent ion-exchange resins and perlite mixture, in decommissioning waste (construction concrete, sand, stainless steel and serpentinite and irradiated graphite from the Ignalina NPP has been performed. The samples for measurement of the specific activity of 14C and 36Cl were obtained from the selected places, where the highest values of the dose rate and the activity concentrations of gamma emitters were found. The performed study of the total 14C and 36Cl activity concentrations was based on estimated chemical forms of 14C (inorganic and organic compounds and 36Cl as Cl- ion. The tested methods used in this study were found to be suitable for estimation of activity concentrations of measured radionuclides.

  19. Systematization of nuclear fuel facility decommissioning technology

    Energy Technology Data Exchange (ETDEWEB)

    Sugitsue, Noritake [Japan Nuclear Cycle Development Inst., Ningyo Toge Environmental Engineering Center, Kamisaibara, Okayama (Japan)

    2001-09-01

    In the Ningyo-Toge Environmental Engineering Center, the nature of all decommissioning works is clarified and, as an information base for planning the promotion of efficiency of a work, the Decommissioning Engineering System is being developed. The Decommissioning Engineering System consists of a function for performing work support for a decommissioning, a function for gathering information results of the decommissioning technology and a general evaluation function for the decommissioning plan on the basis of facilities information collected by three-dimensional CAD. (author)

  20. Unexploded ordnance issues at Aberdeen Proving Ground: Background information

    Energy Technology Data Exchange (ETDEWEB)

    Rosenblatt, D.H.

    1996-11-01

    This document summarizes currently available information about the presence and significance of unexploded ordnance (UXO) in the two main areas of Aberdeen Proving Ground: Aberdeen Area and Edgewood Area. Known UXO in the land ranges of the Aberdeen Area consists entirely of conventional munitions. The Edgewood Area contains, in addition to conventional munitions, a significant quantity of chemical-munition UXO, which is reflected in the presence of chemical agent decomposition products in Edgewood Area ground-water samples. It may be concluded from current information that the UXO at Aberdeen Proving Ground has not adversely affected the environment through release of toxic substances to the public domain, especially not by water pathways, and is not likely to do so in the near future. Nevertheless, modest but periodic monitoring of groundwater and nearby surface waters would be a prudent policy.

  1. Basic Research about Calculation of the Decommissioning Unit Cost based on The KRR-2 Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Hee-Seong; Ha, Jea-Hyun; Jin, Hyung-Gon; Park, Seung-Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The KAERI be used to calculate the decommissioning cost and manage the data of decommissioning activity experience through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). Some country such as Japan and The United States have the information for decommissioning experience of the NPP and publish reports on decommissioning cost analysis. These reports as valuable data be used to compare with the decommissioning unit cost. In particular, need a method to estimate the decommissioning cost of the NPP because there is no decommissioning experience of NPP in case of Korea. makes possible to predict the more precise prediction about the decommissioning unit cost. But still, there are many differences on calculation for the decommissioning unit cost in domestic and foreign country. Typically, it is difficult to compare with data because published not detailed reports. Therefore, field of estimation for decommissioning cost have to use a unified framework in order to the decommissioning cost be provided to exact of the decommissioning cost.

  2. A Decommissioning Information Management System

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Hong, S. B.; Chung, U. S.; Park, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    In 1996, it was determined that research reactors, the KRR-1 and the KRR-2, would be shut down and dismantled. A project for the decommissioning of these reactors was launched in January 1997 with the goal of a completion by 2008. The total budget of the project was 19.4 million US dollars, including the cost for the waste disposal and for the technology development. The work scopes during the decommissioning project were the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After the removal of the entire radioactivity, the site and buildings will be released for an unconditional use. A separate project for the decommissioning of the uranium conversion plant was initiated in 2001. The plant was constructed for the development of the fuel manufacturing technologies and the localization of nuclear fuels in Korea. It was shut downed in 1993 and finally it was concluded in 2000 that the plant would be decommissioned. The project will be completed by 2008 and the total budget was 9.2 million US dollars. During this project, all vessels and equipment will be dismantled and the building surface will be decontaminated to be utilized as general laboratories.

  3. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  4. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  5. Decommissioning: a problem or a challenge?

    Directory of Open Access Journals (Sweden)

    Mele Irena

    2004-01-01

    Full Text Available With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste management programme for each nuclear facility in time, and financial provisions for implementing such programme should be provided. In this paper a presentation of current decommissioning experience in Slovenia is given. The main problems and difficulties in decommissioning of the Žirovski Vrh Uranium Mine are exposed and the lesson learned from this case is presented. The preparation of the decommissioning programme for the Nuclear Power Plant Krško is also described, and the situation at the TRIGA research reactor is briefly discussed.

  6. 33 CFR 334.140 - Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md.

    Science.gov (United States)

    2010-07-01

    ....140 Chesapeake Bay; U.S. Army Proving Ground Reservation, Aberdeen, Md. (a) Restricted area defined. The following indicates the limits of the waters of or adjacent to the Aberdeen Proving Ground, Maryland, and inside of which boundaries will lie the restricted area known as the Aberdeen Proving...

  7. 78 FR 60238 - Proposed Modification and Establishment of Restricted Areas; Aberdeen Proving Ground, MD

    Science.gov (United States)

    2013-10-01

    ...; Aberdeen Proving Ground, MD AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of proposed..., within the existing restricted areas R-4001A and R- 4001B, at the U.S. Army's Aberdeen Proving Ground in... nonparticipating aircraft from a hazard to navigation in the Aberdeen Proving Ground airspace. DATES: Comments......

  8. Basic Research on Selecting ISDC Activity for Decommissioning Costing in KRR-2 Decommissioning Project Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Hee-Seong; Jin, Hyung-Gon; Park, Seung-Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    KAERI is performing research for calculation of expected time of a decommissioning work and evaluation of decommissioning cost and this research calculate a decommissioning work unit productivity based on the experience data of decommissioning activity for KRR-2. The KAERI be used to calculate the decommissioning cost and manage the experience data from the decommissioning activity through the Decommissioning Information Management System (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), and Decommissioning Work-unit Productivity Calculation System (DEWOCS). In this paper, the methodology was presented how select the ISDC activities in dismantling work procedures of a 'removal of radioactive concrete'. The reason to select the 'removal of radioactive concrete' is main key activity and generates the amount of radioactive waste. This data will take advantage of the cost estimation after the code for the selected items derived ISDC. There are various efforts for decommissioning costing in each country. In particular, OECD/NEA recommends decommissioning cost estimation using the ISDC and IAEA provides for Cost Estimation for Research Reactors in Excel (CERREX) program that anyone is easy to use the cost evaluation from a limited decommissioning experience in domestic. In the future, for the decommissioning cost evaluation, the ISDC will be used more widely in a strong position. This paper has described a method for selecting the ISDC item from the actual dismantling work procedures.

  9. Nuclear decommissioning planning, execution and international experience

    CERN Document Server

    2012-01-01

    A title that critically reviews the decommissioning and decontamination processes and technologies available for rehabilitating sites used for nuclear power generation and civilian nuclear facilities, from fundamental issues and best practices, to procedures and technology, and onto decommissioning and decontamination case studies.$bOnce a nuclear installation has reached the end of its safe and economical operational lifetime, the need for its decommissioning arises. Different strategies can be employed for nuclear decommissioning, based on the evaluation of particular hazards and their attendant risks, as well as on the analysis of costs of clean-up and waste management. This allows for decommissioning either soon after permanent shutdown, or perhaps a long time later, the latter course allowing for radioactivity levels to drop in any activated or contaminated components. It is crucial for clear processes and best practices to be applied in decommissioning such installations and sites, particular where any ...

  10. Decommissioning: a United Kingdom perspective

    Energy Technology Data Exchange (ETDEWEB)

    Haworth, A.; Reed, D.L.; Bleeze, A. [Health and Safety Executive, London (United Kingdom)

    1995-12-31

    The paper considers the United Kingdom legislative framework relevant to decommissioning of facilities on nuclear licensed sites. It describes the various legislative bodies involved in regulating this activity and the inspectorate concerned. The licensing regime is described in some detail highlighting the UK arrangements whereby a license is granted for the site upon which nuclear facilities are planned or exist. The license remains in place throughout the life of the plant on the site: from initial planning through to the end of decommissioning. A site (of part of) is not de-licensed until it can be stated that there has ceased to be any danger from ionising radiations from anything on the site (or appropriate part of the site). The final part of the paper considers the changes arising from the commercialization of the nuclear power industry in UK and the restatement of the Nuclear Installation Inspectorate`s policy on decommissioning which has arisen as a result of a review made in response to these changes. (author).

  11. Research in decommissioning techniques for nuclear fuel cycle facilities in JNC. 7. JWTF decommissioning techniques

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-02-01

    Decommissioning techniques such as radiation measuring and monitoring, decontamination, dismantling and remote handling in the world were surveyed to upgrading technical know-how database for decommissioning of Joyo Waste Treatment Facility (JWTF). As the result, five literatures for measuring and monitoring techniques, 14 for decontamination and 22 for dismantling feasible for JWTF decommissioning were obtained and were summarized in tables. On the basis of the research, practical applicability of those techniques to decommissioning of JWTF was evaluated. This report contains brief surveyed summaries related to JWTF decommissioning. (H. Itami)

  12. Decommissioning Project for the Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Paik, S. T. (and others)

    2009-02-15

    In 2008, tried to complete the whole decommissioning project of KRR-1 and KRR-2 and preparing work for memorial museum of KRR-1 reactor. Now the project is delayed for 3 months because of finding unexpected soil contamination around facility and treatment of. To do final residual radioactivity assessment applied by MARSSIM procedure. Accumulated decommissioning experiences and technologies will be very usefully to do decommissioning other nuclear related facility. At the decommissioning site of the uranium conversion plant, the decontamination of the dismantled carbon steel waste are being performed and the lagoon 1 sludge waste is being treated this year. The technologies and experiences obtained from the UCP dismantling works are expected to apply to other fuel cycle facilities decommissioning. The lagoon sludge treatment technology is the first applied technology in the actual field and it is expected that this technology could be applied to other country.

  13. Genetic characterization of Aberdeen Angus cattle using molecular markers

    Directory of Open Access Journals (Sweden)

    Vasconcellos Luciana Pimentel de Mello Klocker

    2003-01-01

    Full Text Available Aberdeen Angus beef cattle from the Brazilian herd were studied genetically using restriction fragment length polymorphism (RFLP of the kappa-casein - HinfI (CSN3 - HinfI, beta-lactoglobulin - HaeIII (LGB - HaeIII and growth hormone AluI (GH- AluI genes, as well as four microsatellites (TEXAN15, CSFM50, BM1224 and BM7160. The RFLP genotypes were determined using the polymerase chain reaction (PCR followed by digestion with restriction endonucleases and electrophoresis in agarose gels. With the exception of the microsatellite BM7160, which was analyzed in an automatic sequencer, the PCR products were genotyped by silver staining. The allele and genotype frequencies, heterozygosities and gene diversity were estimated. The values for these parameters of variability were comparable to other cattle breeds. The genetic relationship of the Aberdeen Angus to other breeds (Caracu, Canchim, Charolais, Guzerath, Gyr, Nelore, Santa Gertrudis and Simmental was investigated using Nei's genetic distance. Cluster analysis placed the Aberdeen Angus in an isolated group in the Bos taurus breeds branch. This fact is in agreement with the geographic origin of this breed.

  14. Deactivation, Decontamination and Decommissioning Project Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

    This report is a compilation of summary descriptions of Deactivation, Decontamination and Decommissioning, and Surveillance and Maintenance projects planned for inactive facilities and sites at the INEEL from FY-2002 through FY-2010. Deactivations of contaminated facilities will produce safe and stable facilities requiring minimal surveillance and maintenance pending further decontamination and decommissioning. Decontamination and decommissioning actions remove contaminated facilities, thus eliminating long-term surveillance and maintenance. The projects are prioritized based on risk to DOE-ID, the public, and the environment, and the reduction of DOE-ID mortgage costs and liability at the INEEL.

  15. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW.

  16. Decommissioning of DR 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2006-01-15

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  17. Sellafield Decommissioning Programme - Update and Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    Lutwyche, P. R.; Challinor, S. F.

    2003-02-24

    The Sellafield site in North West England has over 240 active facilities covering the full nuclear cycle from fuel manufacture through generation, reprocessing and waste treatment. The Sellafield decommissioning programme was formally initiated in the mid 1980s though several plants had been decommissioned prior to this primarily to create space for other plants. Since the initiation of the programme 7 plants have been completely decommissioned, significant progress has been made in a further 16 and a total of 56 major project phases have been completed. This programme update will explain the decommissioning arrangements and strategies and illustrate the progress made on a number of the plants including the Windscale Pile Chimneys, the first reprocessing plan and plutonium plants. These present a range of different challenges and requiring approaches from fully hands on to fully remote. Some of the key lessons learned will be highlighted.

  18. Risk Management of Large Component in Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Nah, Kyung Ku; Kim, Tae Ryong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    The need for energy, especially electric energy, has been dramatically increasing in Korea. Therefore, a rapid growth in nuclear power development has been achieved to have about 30% of electric power production. However, such a large nuclear power generation has been producing a significant amount of radioactive waste and other matters such as safety issue. In addition, owing to the severe accidents at the Fukushima in Japan, public concerns regarding NPP and radiation hazard have greatly increased. In Korea, the operation of KORI 1 has been scheduled to be faced with end of lifetime in several years and Wolsong 1 has been being under review for extending its life. This is the reason why the preparation of nuclear power plant decommissioning is significant in this time. Decommissioning is the final phase in the life-cycle of a nuclear facility and during decommissioning operation, one of the most important management in decommissioning is how to deal with the disused large component. Therefore, in this study, the risk in large component in decommissioning is to be identified and the key risk factor is to be analyzed from where can be prepared to handle decommissioning process safely and efficiently. Developing dedicated acceptance criteria for large components at disposal site was analyzed as a key factor. Acceptance criteria applied to deal with large components like what size of those should be and how to be taken care of during disposal process strongly affect other major works. For example, if the size of large component was not set up at disposal site, any dismantle work in decommissioning is not able to be conducted. Therefore, considering insufficient time left for decommissioning of some NPP, it is absolutely imperative that those criteria should be laid down.

  19. Decommissioning of the BR3 PWR

    Energy Technology Data Exchange (ETDEWEB)

    Massaut, V.; Klein, M

    1998-07-01

    The objectives, programme and main achievements of SCK-CEN's decommissioning programme in 1997 are summarised. Particular emphasis is on the BR3 decommissioning project. In 1997, auxiliary equipment and loops were dismantled; concrete antimissile slabs were decontaminated; the radiology of the primary loop was modelled; the quality assurance procedure for dismantling loops and equipment were implemented; a method for the dismantling of the reactor pressure vessel was selected; and contaminated thermal insulation of the primary loop containing asbestos was removed.

  20. Decommissioning of an irradiation unit

    Energy Technology Data Exchange (ETDEWEB)

    Richards, A.G. [Radiation Protection and Safety Services, Univ. of Leeds, Leeds (United Kingdom)

    2000-05-01

    Distributed throughout hospital, research establishments in the United Kingdom and many other countries are Irradiation Units and Teletherapy machines used for either research purposes or treatment of patients for radiotherapy. These Irradiation Units and Teletherapy machines are loaded with radioactive sources of either Cobalt 60 or Caesium 137. The activity of these sources can range from 1 Terabecquerel up to 100 Terabecquerels or more. Where it is possible to load the radioactive sources without removal from the shielded container into a transport package which is suitable for transport decommissioning of a Teletherapy machine is not a major exercise. When the radioactive sources need to be unloaded from the Irradiation Unit or Teletherapy machine the potential exists for very high levels of radiation. The operation outlined in the paper involved the transfer from an Irradiation Unit to a transport package of two 3.25 Terabecquerel sources of Cobalt 60. The operation of the removal and transfer comes within the scope of the United Kingdom Ionising Radiation Regulations 1985 which were made following the Recommendations of the International Commission on Radiological Protection. This paper illustrates a safe method for this operation and how doses received can be kept within ALARA. (author)

  1. Development Of Decommissioning Information Management System for 101 HWRR

    Institute of Scientific and Technical Information of China (English)

    Yi Song

    2016-01-01

    Decommissioning of 101 Heavy Water Research Reactor (HWRR) is radioactive and high-risk project which has to consider the effects of radiation and nuclear waste disposal, so the information system covering 101 HWRR decommissioning project must be established to ensure safety of the project. In this study, by col ecting the decommissioning activity data to establish the decommissioning database, and based on the database to develop information management system.

  2. Decommissioning in western Europe; Kaernkraftsavveckling i Vaesteuropa

    Energy Technology Data Exchange (ETDEWEB)

    Lundqvist, K. [Castor arbetslivskonsulter AB, Stockholm (Sweden)

    1999-12-01

    This report gives an overview of the situation in Western Europe. The original aim was to focus on organisational and human issues with regard to nuclear reactor decommissioning, but very few articles were found. This is in sharp contrast to the substantial literature on technical issues. While most of the reports on decommissioning have a technical focus, several provide information on regulatory issues, strategies and 'state of the art'. The importance of the human and organizational perspective is however discovered, when reading between the lines of the technical publications, and especially when project managers summarize lessons learned. The results are to a large extent based on studies of articles and reports, mainly collected from the INIS database. Decommissioning of nuclear facilities started already in the sixties, but then mainly research and experimental facilities were concerned. Until now about 70 reactors have been shutdown world-wide. Over the years there have been plenty of conferences for exchanging experiences mostly about technical matters. Waste Management is a big issue. In the 2000s there will be a wave of decommissioning when an increasing amount of reactors will reach the end of their calculated lifetime (40 years, a figure now being challenged by both life-extension and pre-shutdown projects). Several reactors have been shut-down for economical reasons. Shutdown and decommissioning is however not identical. A long period of time can sometimes pass before an owner decides to decommission and dismantle a facility. The conditions will also differ depending on the strategy, 'immediate dismantling' or 'safe enclosure'. If immediate dismantling is chosen the site can reach 'green-field status' in less than ten years. 'Safe enclosure', however, seems to be the most common strategy. There are several pathways, but in general a safe store is constructed, enabling the active parts to remain in safe

  3. Decommissioning of DR 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strufe, N.

    2009-02-15

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  4. Decontamination, decommissioning, and vendor advertorial issue, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

  5. Validation of Decommissioning Engineering System Application against KRR-2

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho; Ha, Jaehyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES.

  6. Sodium Reactor Experiment decommissioning. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  7. Decontamination and decommissioning of Shippingport commercial reactor

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, J. [Dept. of Energy, Pittsburgh, PA (United States)

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  8. Consideration of ISDC for Decommissioning Cost Estimation

    Energy Technology Data Exchange (ETDEWEB)

    Cho, W. H.; Park, S. K.; Choi, Y. D.; Kim, I. S.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    In 2009, they decided to update the Yellow Book, and began to update it by analyzing user experiences. They found that several countries have adopted the proposed standardized cost structure for the production of cost estimates directly or for mapping national estimates onto a common structure. They also made conclusions that more detailed advice should be given on the use of the standardized structure and on the definition of cost items to avoid ambiguity. The revised cost structure, to be known as the International Structure for Decommissioning Costing (ISDC), was published in 2012. The standardized cost structure developed in the report may be used for estimating the costs of decommissioning of any type of nuclear facility. We analyzed this standardized cost structure (ISDC) and applied it to DECOMMIS which was developed by KAERI. The appropriate estimation system for domestic application was examined by comparing the estimation results. KAERI made WBS code in DECOMMIS and data obtained during decommissioning work of KRR2 and UCP. Recently the IAEA updated the decommissioning cost items and its structure by ISDC. The cost estimation items of the DECOMMIS were applied to ISDC structure. For applying, the ISDC code compared with WBS code of DECOMMIS as on text of the activity name from daily report basis. The mapping result of the ISDC items to WBS code of the DECOMMIS is much different. AS results of this study that it need the corresponding cost category which classified in accordance with the national standard price estimates.

  9. Financing strategies for nuclear power decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1980-07-01

    The report analyzes several alternatives for financing the decommissioning of nuclear power plants from the point of view of assurance, cost, equity, and other criteria. Sensitivity analyses are performed on several important variables and possible impacts on representative companies' rates are discussed and illustrated.

  10. 75 FR 80697 - Nuclear Decommissioning Funds

    Science.gov (United States)

    2010-12-23

    ... collection of information unless the collection of information displays a valid OMB control number. Books or... books on the asset. Section 1.468A- 8T(b)(3)(ii) of the temporary regulations provides that, in the case... connection with the preparation for decommissioning, such as engineering and other planning expenses, and...

  11. Development of the Decommissioning Project Management System, DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  12. NMSS handbook for decommissioning fuel cycle and materials licensees

    Energy Technology Data Exchange (ETDEWEB)

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M. [and others

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  13. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    Energy Technology Data Exchange (ETDEWEB)

    Serrato, Michael G. [Savannah River National Laboratory, Savannah River Nuclear Solutions, Aiken, SC 29808 (United States); Musall, John C.; Bergren, Christopher L. [Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)

    2013-07-01

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m{sup 3}) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and

  14. Decommissioning of the Salaspils Research Reactor

    Directory of Open Access Journals (Sweden)

    Abramenkovs Andris

    2011-01-01

    Full Text Available In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor and to dispense with nuclear energy in the future. The reactor has been out of operation since July 1998. A conceptual study on the decommissioning of the Salaspils Research Reactor was drawn up by Noell-KRC-Energie- und Umwelttechnik GmbH in 1998-1999. On October 26th, 1999, the Latvian government decided to start the direct dismantling to “green-field” in 2001. The upgrading of the decommissioning and dismantling plan was carried out from 2003-2004, resulting in a change of the primary goal of decommissioning. Collecting and conditioning of “historical” radioactive wastes from different storages outside and inside the reactor hall became the primary goal. All radioactive materials (more than 96 tons were conditioned for disposal in concrete containers at the radioactive wastes depository “Radons” at the Baldone site. Protective and radiation measurement equipment of the personnel was upgraded significantly. All non-radioactive equipment and materials outside the reactor buildings were released for clearance and dismantled for reuse or conventional disposal. Contaminated materials from the reactor hall were collected and removed for clearance measurements on a weekly basis.

  15. Unrestricted re-use of decommissioned nuclear laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Cornelissen, R.; Noynaert, L.; Harnie, S.; Marien, J.

    1996-09-18

    A decommissioning strategy was developed by the Belgian Nuclear Research Centre SCK/CEN. In this strategy decommissioning works are limited to the radioactive parts of the nuclear installation. After obtaining an attestation for unrestricted reuse of the building after removal of all radioactivity, the building can be used for new industrial purposes outside the nuclear field. The decommissioning activities according to this strategy have been applied in four buildings. The results are described.

  16. Initial decommissioning planning for the Budapest research reactor

    Directory of Open Access Journals (Sweden)

    Toth Gabor

    2011-01-01

    Full Text Available The Budapest Research Reactor is the first nuclear research facility in Hungary. The reactor is to remain in operation for at least another 13 years. At the same time, the development of a decommissioning plan is a mandatory requirement under national legislation. The present paper describes the current status of decommissioning planning which is aimed at a timely preparation for the forthcoming decommissioning of the reactor.

  17. Development of a decommissioning strategy for the MR research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bylkin, Boris; Gorlinsky, Yury; Kolyadin, Vyacheslav; Pavlenko, Vitaly [RRC Kurchatov Institute, Moscow (Russian Federation); Craig, David; Fecitt, Lorna [NUKEM Limited, Dounreay (United Kingdom); Harman, Neil; Jackson, Roger [Serco Technical and Assurance Services, Warrington (United Kingdom); Lobach, Yury [Inst. for Nuclear Research of NASU, Kiev (Ukraine)

    2010-03-15

    A description of the selected decommissioning strategy for the research reactor MR at the site of the Kurchatov Institute in Moscow is presented. The MR reactor hall is planned to be used as a temporary fuel store for the other research reactors on the site. On the basis of the site-specific conditions and over-all decommissioning goals, it was identified that phased immediate decommissioning is the preferable option. The current status of the reactor, expected final conditions and the sequence of decommissioning works are shown. (orig.)

  18. The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

    Energy Technology Data Exchange (ETDEWEB)

    Meek, N.C.; Ingram, S.; Page, J. [BNFL Environmental Services (United Kingdom)

    2003-07-01

    BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] {yields} [Review project and conduct Characterisation review of power station] {yields} [Identify work packages] {yields} [Set up WBS to level 3] {yields} [Assign work packages] {yields} [Update WBS to level 4] {yields}[Develop cost model] {yields} [Develop logic network] {yields} [Develop risk management procedure] ] {yields

  19. Decontamination and decommissioning project for the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. (and others)

    2007-02-15

    The final goal of this project is to complete the decommissioning of the Korean Research Reactor no.1 and no. 2(KRR-1 and 2) and uranium conversion plant safely and successfully. The goal of this project in 2006 is to complete the decontamination of the inside reactor hall of the KRR-2 which will be operating as a temporary storage for the radioactive waste until the construction and operation of the national repository site. Also the decommissioning work of the KRR-1 and auxiliary facilities is being progress. As the compaction of decommissioning project is near at hand, a computer information system was developed for a systematically control and preserve a technical experience and decommissioning data for the future reuse. The nuclear facility decommissioning, which is the first challenge in Korea, is being closed to the final stages. We completed the decommissioning of all the bio-shielding concrete for KRR-2 in 2005 and carried out the decontamination and waste material grouping of the roof, wall and bottom of the reactor hall of the KRR-2. The decommissioning for nuclear facility were demanded the high technology, remote control equipment and radioactivity analysis. So developed equipment and experience will be applied at the decommissioning for new nuclear facility in the future.

  20. Treatment of Decommissioning Combustible Wastes with Incineration Technology

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. Y. Min; Yang, D. S.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The aim of the paper is current status of management for the decommissioning radioactive combustible and metal waste in KAERI. In Korea, two decommissioning projects were carried out for nuclear research facilities (KRR-1 and KRR-2) and a uranium conversion plant (UCP). Through the two decommissioning projects, lots of decommissioning wastes were generated. Decommissioning waste can be divided into radioactive waste and releasable waste. The negative pressure of the incineration chamber remained constant within the specified range. Off-gas flow and temperature were maintained constant or within the desired range. The measures gases and particulate materials in the stack were considerably below the regulatory limits. The achieved average volume reduction ratio during facility operation is about 1/65.

  1. Standard Guide for Radiation Protection Program for Decommissioning Operations

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of...

  2. U.S. experience with organizational issues during decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Durbin, N.E. [MPD Consulting, Kirkland, WA (United States); Harty, R. [Battelle Pacific Northwest National Laboratory, Richland, WA (United States)

    1998-01-01

    The report provides information from a variety of sources, including interviews with US NRC management and staff, interviews and discussions with former employees of a decommissioned plant, discussions with subject matter experts, and relevant published documents. The NRC has modified its rule regarding decommissioning requirements. Two key reasons for these modifications are that plants have been decommissioning early and for economic reasons instead of at the end of their license period and, a desire for a more efficient rule that would more effectively use NRC staff. NRC management and staff expressed the opinion that resource requirements for the regulatory have been higher than anticipated. Key observations about decommissioning included that: The regulator faces new challenges to regulatory authority and performance during decommissioning. The public concern over decommissioning activities can be very high. There are changes in the types of safety concerns during decommissioning. It is important to balance planning and the review of plans with verification of activities. There are important changes in the organizational context at the plant during decommissioning. Retention of key staff is important. In particular, the organizational memory about the plant that is in the staff should not be lost. Six key areas of risk during decommissioning are fuel storage, potential accidents that could cause an offsite release, inappropriate release of contaminated material, radiation protection of workers, industrial accidents, and shipment of hazardous materials. Deconstruction of one unit while a co-located unit is still operating could create risks with regard to shared systems, specific risks of dismantling activities and coordination and management. Experience with co-located units at one site in the US was that there was a lack of attention to the decommissioning plant.

  3. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  4. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  5. DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Murray, A.; Abbott, H.

    2003-02-27

    Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

  6. Decontamination and Decommissioned Small Nuclear AIP Hybrid Systems Submarines

    Directory of Open Access Journals (Sweden)

    Guangya Liu

    2013-11-01

    Full Text Available Being equipped with small reactor AIP is the trend of conventional submarine power in 21st century as well as a real power revolution in conventional submarine. Thus, the quantity of small reactor AIP Submarines is on the increase, and its decommissioning and decontamination will also become a significant international issue. However, decommissioning the small reactor AIP submarines is not only a problem that appears beyond the lifetime of the small reactor nuclear devices, but the problem involving the entire process of design, construction, running and closure. In the paper, the problem is explored based on the conception and the feasible decommissioning and decontamination means are supplied to choose from.

  7. Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

    Energy Technology Data Exchange (ETDEWEB)

    Dettmers, Dana Lee; Eide, Steven Arvid

    2002-10-01

    An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

  8. Decontamination, decommissioning, and vendor advertorial issue, 2008

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2008-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.

  9. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program.

  10. Optimization of Decommission Strategy for Offshore Wind Farms

    DEFF Research Database (Denmark)

    Hou, Peng; Hu, Weihao; Soltani, Mohsen;

    2016-01-01

    The life time of offshore wind farm is around 20 years. After that, the whole farm should be decommissioned which is also one of the main factors that contribute to the high investment. In order to make a costeffective wind farm, a novel optimization method for decommission is addressed in this p......The life time of offshore wind farm is around 20 years. After that, the whole farm should be decommissioned which is also one of the main factors that contribute to the high investment. In order to make a costeffective wind farm, a novel optimization method for decommission is addressed...... in this paper. Instead of abandoning the foundations after the wind farm is running out of its life cycle, the proposed method can make good use of the existing facilities so that the cost of energy (COE) can be reduced. The results show that 12.93% reduction of COE can be realized by using the proposed method....

  11. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  12. Solid Waste from the Operation and Decommissioning of Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Marilyn Ann [Georgia Inst. of Technology, Atlanta, GA (United States); D' Arcy, Daniel [Georgia Inst. of Technology, Atlanta, GA (United States); Lapsa, Melissa Voss [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sharma, Isha [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Li, Yufei [Georgia Inst. of Technology, Atlanta, GA (United States)

    2017-01-05

    This baseline report examines the solid waste generated by the U.S. electric power industry, including both waste streams resulting from electricity generation and wastes resulting from the decommissioning of power plants

  13. Lessons Learned from the NASA Plum Brook Reactor Facility Decommissioning

    Science.gov (United States)

    2010-01-01

    NASA has been conducting decommissioning activities at its PBRF for the last decade. As a result of all this work there have been several lessons learned both good and bad. This paper presents some of the more exportable lessons.

  14. The Decommissioning of the Trino Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

    2002-02-27

    Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise

  15. BCD: a wiki-based decommissioning knowledge management tool

    Energy Technology Data Exchange (ETDEWEB)

    Fontaine, V.; Coudouneau, L.; Goursaud, V. [CEA Marcoule (DEN/MAR/DPAD/SECAD), 30 (France)

    2008-07-01

    Knowledge management allows decommissioning stakeholders to take advantage of past experience (in terms of efficiency, quality, safety, cost, etc.), avoid repeating previous errors, and identify good ideas and practices. It is usually broken down into three processes: collecting information, supplementing and enriching it, and making it available to all decommissioning stakeholders. The CEA has been collecting and centralizing data for many years: the first qualitative assessment of operational experience began in 1991. However, the documents collected were not always relevant for this assessment and, for lack of enrichment and distribution, were generally not used to a significant extent. In order to take advantage of the existing and future body of knowledge and to share this knowledge among decommissioning stakeholders, the CEA decommissioning review unit decided to develop an intranet site known as BCD (from the French acronym for Central Decommissioning Database) using the same wiki technology as the collaborative web encyclopedia, Wikipedia. The objective of BCD is to develop a decommissioning encyclopedia comprising definitions and terminology, the regulatory framework, the lessons of experience with technical or contractual projects, guidelines, statements of results, etc. This article describes BCD and its potential, together with the results observed to date and its prospects for future development. (authors)

  16. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  17. An overview of U.S. decommissioning experience -- A basic introduction

    Energy Technology Data Exchange (ETDEWEB)

    Boing, L.E.

    1998-03-09

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

  18. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2001-01-01

    Fundamental concepts on the life extension of the nuclear power plant and decommissioning optimization were established from the domestic abroad information and case analyses. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the standard of the decommissioning(decontamination dismantling) regulation. Moreover, basics were set for the decommissioning of domestic nuclear power plants and research reactors from the analyses on the decommissioning technology and precedence.

  19. Decontamination and Decommissioning Project for the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. and others

    2006-02-15

    The final goal of this project is to complete safely and successfully the decommissioning of the Korean Research Reactor no.1 (KRR-1) and the Korean Research Reactor no.2 (KRR-2), and uranium conversion plant (UCP). The dismantling of the reactor hall of the KRR-2 was planned to complete till the end of 2004, but it was delayed because of a few unexpected factors such as the development of a remotely operated equipment for dismantling of the highly radioactive parts of the beam port tubes. In 2005, the dismantling of the bio-shielding concrete structure of the KRR-2 was finished and the hall can be used as a temporary storage space for the radioactive waste generated during the decommissioning of the KRR-1 and KRR-2. The cutting experience of the shielding concrete by diamond wire saw and the drilling experience by a core boring machine will be applied to another nuclear facility dismantling. An effective management tool of the decommissioning projects, named DECOMIS, was developed and the data from the decommissioning projects were gathered. This system provided many information on the daily D and D works, waste generation, radiation dose, etc., so an effective management of the decommissioning projects is expected from next year. The operation experience of the uranium conversion plant as a nuclear fuel cycle facility was much contributed to the localization of nuclear fuels for both HWR and PWR. It was shut down in 1993 and a program for its decontamination and dismantling was launched in 2001 to remove all the contaminated equipment and to achieve the environment restoration. The decommissioning project is expected to contribute to the development of the D and D technologies for the other domestic fuel cycle facilities and the settlement of the new criteria for decommissioning of the fuel cycle related facilities.

  20. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hlohowskyj, I.; Hayse, J.; Kuperman, R.; Van Lonkhuyzen, R.

    2000-02-25

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment.

  1. Early life predictors of childhood intelligence: evidence from the Aberdeen children of the 1950s study

    OpenAIRE

    Lawlor,D.A.; Batty, G D; Morton, S M B; Deary, I.J.; Macintyre, S.; Ronalds, G.; Leon, D. A.

    2005-01-01

    Objective: To identify the early life predictors of childhood intelligence. \\ud \\ud Design: Cohort study of 10 424 children who were born in Aberdeen (Scotland) between 1950 and 1956. \\ud \\ud Results: Social class of father around the time of birth, gravidity, maternal age, maternal physical condition, whether the child was born outside of marriage, prematurity, intrauterine growth, and childhood height were all independently associated with childhood intelligence at ages 7, 9, and 11. The ef...

  2. Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

    2014-10-15

    A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas.

  3. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant. [Appendices only

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Volume 2 comprises six appendices on: facility description; residual radioactivity inventory estimates; description and contamination levels of reference site; derivation of residual contamination levels; decommissioning mode detail; and decommissioning safety assessment details.

  4. DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS

    Energy Technology Data Exchange (ETDEWEB)

    Bollinger, J; William Austin, W; Larry Koffman, L

    2007-09-17

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

  5. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

  6. 77 FR 75198 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Science.gov (United States)

    2012-12-19

    ... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method...) 1.185, ``Standard Format and Content for Post-shutdown Decommissioning Activities Report,''...

  7. Radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

    2010-07-15

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  8. Establishment the code for prediction of waste volume on NPP decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Cho, W. H.; Park, S. K.; Choi, Y. D.; Kim, I. S.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In practice, decommissioning waste volume can be estimated appropriately by finding the differences between prediction and actual operation and considering the operational problem or supplementary matters. So in the nuclear developed countries such as U.S. or Japan, the decommissioning waste volume is predicted on the basis of the experience in their own decommissioning projects. Because of the contamination caused by radioactive material, decontamination activity and management of radio-active waste should be considered in decommissioning of nuclear facility unlike the usual plant or facility. As the decommissioning activity is performed repeatedly, data for similar activities are accumulated, and optimal strategy can be achieved by comparison with the predicted strategy. Therefore, a variety of decommissioning experiences are the most important. In Korea, there is no data on the decommissioning of commercial nuclear power plants yet. However, KAERI has accumulated the basis decommissioning data of nuclear facility through decommissioning of research reactor (KRR-2) and uranium conversion plant (UCP). And DECOMMIS(DECOMMissioning Information Management System) was developed to provide and manage the whole data of decommissioning project. Two codes, FAC code and WBS code, were established in this process. FAC code is the one which is classified by decommissioning target of nuclear facility, and WBS code is classified by each decommissioning activity. The reason why two codes where created is that the codes used in DEFACS (Decommissioning Facility Characterization management System) and DEWOCS (Decommissioning Work-unit productivity Calculation System) are different from each other, and they were classified each purpose. DEFACS which manages the facility needs the code that categorizes facility characteristics, and DEWOCS which calculates unit productivity needs the code that categorizes decommissioning waste volume. KAERI has accumulated decommissioning data of KRR

  9. Integration of improved decontamination and characterization technologies in the decommissioning of the CP-5 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bhattacharyya, S. K.; Boing, L. E.

    2000-02-17

    The aging of research reactors worldwide has resulted in a heightened awareness in the international technical decommissioning community of the timeliness to review and address the needs of these research institutes in planning for and eventually performing the decommissioning of these facilities. By using the reactors already undergoing decommissioning as test beds for evaluating enhanced or new/innovative technologies for decommissioning, it is possible that new techniques could be made available for those future research reactor decommissioning projects. Potentially, the new technologies will result in: reduced radiation doses to the work force, larger safety margins in performing decommissioning and cost and schedule savings to the research institutes in performing the decommissioning of these facilities. Testing of these enhanced technologies for decontamination, dismantling, characterization, remote operations and worker protection are critical to furthering advancements in the technical specialty of decommissioning. Furthermore, regulatory acceptance and routine utilization for future research reactor decommissioning will be assured by testing and developing these technologies in realistically contaminated environments prior to use in the research reactors. The decommissioning of the CP-5 Research Reactor is currently in the final phase of dismantlement. In this paper the authors present results of work performed at Argonne National Laboratory (ANL) in the development, testing and deployment of innovative and/or enhanced technologies for the decommissioning of research reactors.

  10. Development of decontamination, decommissioning and environmental restoration technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Jik; Kwon, H. S.; Kim, G. N. and others

    1999-03-01

    Through the project of 'Development of decontamination, decommissioning and environmental restoration technology', the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

  11. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    Energy Technology Data Exchange (ETDEWEB)

    Williams, D. G.

    2002-02-26

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole.

  12. 18 CFR 2.24 - Project decommissioning at relicensing.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  13. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  14. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    Energy Technology Data Exchange (ETDEWEB)

    Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  15. Initial building investigations at Aberdeen Proving Ground, Maryland: Objectives and methodology

    Energy Technology Data Exchange (ETDEWEB)

    Brubaker, K.L.; Dougherty, J.M.; McGinnis, L.D.

    1994-12-01

    As part of an environmental-contamination source-definition program at Aberdeen Proving Ground, detailed internal and external inspections of 23 potentially contaminated buildings are being conducted to describe and characterize the state of each building as it currently exists and to identify areas potentially contaminated with toxic or other hazardous substances. In addition, a detailed geophysical investigation is being conducted in the vicinity of each target building to locate and identify subsurface structures, associated with former building operations, that are potential sources of contamination. This report describes the objectives of the initial building inspections, including the geophysical investigations, and discusses the methodology that has been developed to achieve these objectives.

  16. Hydrogeologic data for the Canal Creek area, Aberdeen Proving Ground, Maryland, April 1986-March 1988

    Science.gov (United States)

    Oliveros, J.P.; Gernhardt, Patrice

    1989-01-01

    This report is a compilation of hydrologic and geologic data collected for the period April 1986 through March 1988 for the Canal Creek area of Aberdeen Proving Ground, Maryland. Geologic data include lithologic logs for 73 sites and geophysical logs for 71 sites. Hydrologic data consist of hydrographs and synoptic water level measurements. The hydrographs were taken from eight wells that were equipped with continuous water level recorders, and the synoptic water-level measurements were made four times during the study. Well-construction data also are included for 149 observation wells. (USGS)

  17. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    Energy Technology Data Exchange (ETDEWEB)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  18. A Review of the Decommissioning Costs of the Ranstad Site

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff (NAC International, Norcross, GA (United States))

    2009-08-15

    The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary 'bench-marking' studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been compared with actual costs from other relevant decommissioning projects. In this way it has been possible to give a preliminary qualitative statement about the accuracy of the Ranstad cost estimate. The study gives the following lessons learned: 1. The available information suggests that the overall estimated cost may be reasonable, but there are still some points of weakness that need to be elaborated more in detail before a full statement about the adequacy of the forecast cost will be possible. 2. Especially the costs associated with declassification activities warrant further analysis in order to determine there level of accuracy. 3. There exists the possibility that the estimate might be low concerning decontamination, dismantling and planning and institutional work. 4. Further work and analysis is needed in order to develop a more transparent cost estimate in which the stakeholders can have the highest confidence. 5. A new bidding procedure for the conventional demolition may result in lower estimated costs. Hence, it would be beneficial to obtain an updated estimate based on at least more than one quotation. 6. The method of addressing uncertainty and risk should be more connected to the logistics of specific decommissioning activities, in order to be more transparent and clearer in details. There is a need for further study to develop a better estimate. In the short run follow-up work needs to be undertaken to provide a better understanding of what are the major contributors to risk and cost drivers in the planned decommissioning process at the Ranstad

  19. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 6 - PRESENTATION OF THE DECOMMISSIONING DEVICE

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2015-05-01

    Full Text Available The objective of this paper is to present a possible solution for the designing of a device for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The decommissioning activities are dismantling, demolition, controlled removal of equipment, components, conventional or hazardous waste (radioactive, toxic in compliance with the international basic safety standards on radiation protection. One as the most important operation in the final phase of the nuclear reactor dismantling is the decommissioning of fuel channels. For the fuel channels decommissioning should be taken into account the detailed description of the fuel channel and its components, the installation documents history, adequate radiological criteria for decommissioning guidance, safety and environmental impact assessment, including radiological and non-radiological analysis of the risks that can occur for workers, public and environment, the description of the proposed program for decommissioning the fuel channel and its components, the description of the quality assurance program and of the monitoring program, the equipments and methods used to verify the compliance with the decommissioning criteria, the planning of performing the final radiological assessment at the end of the fuel channel decommissioning. These will include also, a description of the proposed radiation protection procedures to be used during decommissioning. The dismantling of the fuel channel is performed by one device which shall provide radiation protection during the stages of decommissioning, ensuring radiation protection of the workers. The device shall be designed according to the radiation protection procedures. The decommissioning device assembly of the fuel channel components is composed of the device itself and moving platform support for coupling of the selected channel to be dismantled. The fuel channel decommissioning device is an autonomous device designed for

  20. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army`s Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  1. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army's Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  2. Ehrlichia chaffeensis (Rickettsiales: Ehrlichieae) infection in Amblyomma americanum (Acari: Ixodidae) at Aberdeen Proving Ground, Maryland.

    Science.gov (United States)

    Stromdahl, E Y; Randolph, M P; O'Brien, J J; Gutierrez, A G

    2000-05-01

    Human monocytic ehrlichiosis (HME) is a sometimes fatal, emerging tick-borne disease caused by the bacterium Ehrlichia chaffeensis. It is frequently misdiagnosed because its symptoms mimic those of the flu. Current evidence indicates that Amblyomma americanum (L.), the lone star tick, is the major vector of HME. To determine if E. chaffeensis is present in ticks at Aberdeen Proving Ground, MD, questing A. americanum ticks were collected from 33 sites. Nucleic acid was extracted from 34 adult and 81 nymphal pools. Sequences diagnostic for E. chaffeensis from three different loci (16S rRNA, 120-kDa protein, and a variable-length polymerase chain reaction [PCR] target, or VLPT) were targeted for amplification by the PCR. Fifty-two percent of the collection sites yielded pools infected with E. chaffeensis, confirming the presence and widespread distribution of E. chaffeensis at Aberdeen Proving Ground. Analysis with the both the 120-kDa protein primers and the VLPT primers showed that genetic variance exists. A novel combination of variance for the two loci was detected in two tick pools. The pathogenic implications of genetic variation in E. chaffeensis are as yet unknown.

  3. Dr. Auzoux's botanical teaching models and medical education at the universities of Glasgow and Aberdeen.

    Science.gov (United States)

    Olszewski, Margaret Maria

    2011-09-01

    In the 1860s, Dr. Louis Thomas Jérôme Auzoux introduced a set of papier-mâché teaching models intended for use in the botanical classroom. These botanical models quickly made their way into the educational curricula of institutions around the world. Within these institutions, Auzoux's models were principally used to fulfil educational goals, but their incorporation into diverse curricula also suggests they were used to implement agendas beyond botanical instruction. This essay examines the various uses and meanings of Dr. Auzoux's botanical teaching models at the universities of Glasgow and Aberdeen in the nineteenth century. The two main conclusions of this analysis are: (1) investing in prestigious scientific collections was a way for these universities to attract fee-paying students so that better medical accommodation could be provided and (2) models were used to transmit different kinds of botanical knowledge at both universities. The style of botany at the University of Glasgow was offensive and the department there actively embraced and incorporated ideas of the emerging new botany. At Aberdeen, the style of botany was defensive and there was some hesitancy when confronting new botanical ideas.

  4. Development of decommissioning management system for nuclear fuel cycle facilities (DECMAN)

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichirou; Ishijima, Noboru; Tanimoto, Ken-ichi [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-04-01

    In making a plan of decommissioning of nuclear fuel facilities, it is important to optimize the plan on the standpoint of a few viewpoints, that is, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost (they are called evaluation indexes). In the midst of decommissioning, the decommissioning plan would be modified suitably to optimize the evaluation indexes adjusting to progress of the decommissioning. The decommissioning management code (DECMAN), that is support system on computer, has been developed to assist the decommissioning planning. The system calculates the evaluation indexes quantitatively. The system consists of three fundamental codes, facility information database code, technical know-how database code and index evaluation code, they are composed using Oracle' database and 'G2' expert system. The functions of the system are as follows. (1) Facility information database code. Information of decommissioning facility and its rooms, machines and pipes in the code. (2) Technical know-how database code. Technical Information of tools to use in decommissioning work, cutting, dose measure, and decontamination are there. (3) Index evaluation code. User build decommissioning program using above two database codes. The code evaluates five indexes, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost, on planning decommissioning program. Results of calculation are shown in table, chart, and etc. (author)

  5. Current status of decommissioning projects and their strategies in advanced countries

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Park, J. H.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-06-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The number of nuclear facilities to be dismantled will be much increased in future and the decommissioning industries will be enlarged. Keeping pace with this increasing tendency, each country formulated their own strategies and regulation systems, and applied their own technologies. The international organizations such as the IAEA and the OECD/NEA also prepared standards in technologies and regulation upon decommissioning and recommended to adopt them to the decommissioning projects. These strategies and technologies are very different country by country due to the different site dependent conditions and it will not be reasonable to evaluate their merits and weakness. The world wide status of the decommissioning, highlighted on that of 5 countries of USA, UK, France, Germany and Japan because they are advanced counties in nuclear industries, are summarized and their site specific conditions are evaluated. The scopes of the evaluation are decommissioning strategies, licensing procedures and requirements focused on decommissioning plan, waste management, technology development and so on. The detailed decommissioning progresses of several typical example sites were introduced. The activities on decommissioning field of the international organization, increased according to the enlarged decommissioning industries, are also summarized.

  6. Evaluation of the UCP Decommissioning Activities in 2008 using DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Park, J. H; Hwang, D. S.; Lee, K. W.; Chung, U. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-05-15

    In early 1992, Korea Atomic Energy Research Institute (KAERI) decided that the operation of the Uranium Conversion Plant (UCP) would be stopped due to a relatively higher production cost than that of the international market. The conversion plant has been shut down and minimally maintained for the prevention of a contamination by a deterioration of the equipment and the lagoon. In 2000, the decommissioning was finally decided upon and a decommissioning program was launched to complete the following tasks by 2010 with the total budget, 10 million US dollars: planning and assessment of the environmental impact; dismantling of the pipes, tanks, vessels and equipment for a canning or reuse; decontamination of the dismantled metal wastes for release, decontamination of the building for an reuse as an another experimental facility, and the treatment of the sludge waste and the demolition of the lagoon. The decommissioning works started in 2004. The Uranium Conversion Plant building is composed 3 stories and the floor area is 2,950 m{sup 2}. The equipment and facilities consist of chemical reactors such as a dissolver and FBR, tanks, pumps, pipes, and electric and electronic equipment. The radiological conditions before a dismantling were as follows; radiation dose 3x10{sup -4}{approx}3x10{sup -2} mSv/hr, surface contamination of equipment and structure 0.001{approx}3.6 Bq/cm{sup 2}, and surface contamination of concrete 0.01{approx}1.4 Bq/cm{sup 2}. The lagoon is used for store the waste water which generated during an operation. The lagoon consists of two artificial ponds constructed by a concrete structure with a lubber coating and the surface area is 760 m{sup 2}. Total weight of the sludge is about 330 tons. The major compounds are ammonium nitrate, sodium nitrate, calcium nitrate, calcium carbonate, and natural uranium of 1 wt%. Radiological conditions were as follows; radiation dose 1x10{sup -4}{approx}3x10{sup -3} mSv/hr. The DECOMMIS, which is the data base

  7. Offshore Wind Energy Cost Modeling Installation and Decommissioning

    CERN Document Server

    Kaiser, Mark J

    2012-01-01

    Offshore wind energy is one of the most promising and fastest growing alternative energy sources in the world. Offshore Wind Energy Cost Modeling provides a methodological framework to assess installation and decommissioning costs, and using examples from the European experience, provides a broad review of existing processes and systems used in the offshore wind industry. Offshore Wind Energy Cost Modeling provides a step-by-step guide to modeling costs over four sections. These sections cover: ·Background and introductory material, ·Installation processes and vessel requirements, ·Installation cost estimation, and ·Decommissioning methods and cost estimation.  This self-contained and detailed treatment of the key principles in offshore wind development is supported throughout by visual aids and data tables. Offshore Wind Energy Cost Modeling is a key resource for anyone interested in the offshore wind industry, particularly those interested in the technical and economic aspects of installation and decom...

  8. TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING WORKSHOP REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

    2009-06-30

    In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and

  9. Uranium Enrichment: Analysis of Decontamination and Decommissioning Scenarios

    Science.gov (United States)

    1991-11-01

    from a September 1991 report entitled Preliminary Cost Estimate Decontamination & Decommissioning of the Gaseous Diffusion Plants , prepared for DOE by...DOE) three aging uranium enrichment plants . These plants are located in Oak Ridge, Tennessee; Paducah , Kentucky; and Portsmouth, Ohio. On October 16... Diffusion Plants Assessment of Costs for Remedial Actions. This report was prepared for DOE by Martin Marietta Energy Systems, DOE’s management and

  10. Decontamination and decommissioning surveillance and maintenance report for FY 1991

    Energy Technology Data Exchange (ETDEWEB)

    Gunter, David B.; Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D D) Program has three distinct phases: (1) surveillance and maintenance (S M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D D is devoted to S M at each of the sites. Our S M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  11. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    Energy Technology Data Exchange (ETDEWEB)

    Jackson, P.K.; Freemerman, R.L. [Bechtel National, Inc., Oak Ridge, TN (United States)

    1989-11-01

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  12. Comparison of different strategies for decommissioning a tritium laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Dylst, Kris, E-mail: Kris.Dylst@sckcen.be [SCK-CEN, Dismantling, Decontamination and Waste, Boeretang 200, 2400 Mol (Belgium); Slachmuylders, Frederik; Gilissen, Bart [SCK-CEN, Dismantling, Decontamination and Waste, Boeretang 200, 2400 Mol (Belgium)

    2013-10-15

    Highlights: ► Decontamination to below the free release limits is very labour intensive. ► Disposing of contaminated steel to a nuclear melting facility is cost effective. ► It can be advantageous to invest in decontamination of non-steel materials. -- Abstract: Between 2003 and 2009 two rooms that served as tritium laboratory at SCK• CEN and its ventilation system were decommissioned. Initially, the decommissioning strategy was to free release as much materials as possible. However, due to the imposed free release limit this was very labour intensive. Timing restrictions forced us to use a different strategy for the ventilation system. Most of the steel was disposed of to a nuclear melting facility. As a result there was a significant decrease in the required man labour. For the second laboratory room a similar strategy as for the ventilation was used: contaminated steel was disposed of to a nuclear melting facility and other materials that could not be easily decontaminated were disposed of as nuclear waste. At the expense of extra waste generation compared to the first laboratory the decommissioning was done using merely one third of the man hours. Comparison of the used strategies indicated opportunities for cost optimization. Even in absence of time constraints it is best to foresee a safe disposal of metals to a nuclear melting facility, whilst it is worth to invest in the labour intensive decontamination of the other materials to free release them.

  13. Decommissioning of the pool reactor Thetis in Ghent, Belgium

    Energy Technology Data Exchange (ETDEWEB)

    Cortenbosch, Geert; Mommaert, Chantal [Bel V, Brussels (Belgium); Tierens, Hubert; Monsieurs, Myriam; Meierlaen, Isabelle; Strijckmans, Karel [Ghent Univ. (Belgium)

    2016-11-15

    The Thetis research pool reactor (with a nominal power of 150 kW) of the Ghent University was operational from 1967 till December 2003. The first phase of the decommissioning of the reactor, the removal of the spent fuel from the site, took place in 2010. The cumulative dose received was only 404 man . μSv. During the second phase, the transition period between the removal of the spent fuel in 2010 and the start of the decommissioning phase in March 2013, 3-monthly internal inspections and inspections by Bel V, were performed. The third and final decommissioning phase started on March 18, 2013. The total dose received between March 2013 and August 2013 was 1561 man . μSv. The declassification from a Class I installation to a Class II installation was possible by the end of 2015. The activated concrete in the reactor pool will remain under regulatory control until the activation levels are lower than the limits for free release.

  14. Experience on Primary System Decommissioning in Jose Cabrera NPP

    Energy Technology Data Exchange (ETDEWEB)

    Paloma Molleda; Leandro Sanchez; David Rodriguez [ENSA, Cantabria (Spain)

    2015-10-15

    Primary System Decommissioning belongs to DCP(Decommissioning and Closure Plan) works and its scope includes: Steam Generator, Pressurizer, Refrigerant Circuit Pump and Primary Circuit Piping. All these dismantling activities were carried out on site, including preliminary steps before their removal (SAS installations, pre decontaminations, cutting and segmentations, segregations, etc.) and delivery to media/low activity nuclear waste disposal site. There are many cutting techniques available in market (most of them proved with positive results) as well as there are many different approaches about how to manage radioactive wastes in decommissioning projects (containers or great components disposal, containers burial, re fusion, etc.). Both issues are linked and, before starting a new project, it might be positive and quite useful to compare and study previous dismantling experiences, especially the lesson learned chapter. Primary System cut with diamond saw has been a challenge target, not only due to the methodology innovation (since until nowadays, the common use of this technology was performed in cutting concrete walls) because it has a huge range of positive aspects that, in our opinion, are attractive (apart from its mentioned versatility, in terms of cutting on site and every type of material)

  15. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    R. L. Demmer

    2011-04-01

    The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

  16. Radioactive waste from decommissioning of fast reactors (through the example of BN-800)

    Science.gov (United States)

    Rybin, A. A.; Momot, O. A.

    2017-01-01

    Estimation of volume of radioactive waste from operating and decommissioning of fast reactors is introduced. Preliminary estimation has shown that the volume of RW from decommissioning of BN-800 is amounted to 63,000 cu. m. Comparison of the amount of liquid radioactive waste derived from operation of different reactor types is performed. Approximate costs of all wastes disposal for complete decommissioning of BN-800 reactor are estimated amounting up to approx. 145 million.

  17. Operation and dismantling report 2004 for Danish Decommissioning; Drifts- og afviklingsrapport 2004 - Dansk Dekommissionering

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-01

    The report describes the operations at Danish Decommissioning (DD) that are essential for the nuclear inspection authorities' assessment of safety related issues. The report presents an account of safety and of the work at DD, including the decommissioning projects in 2004 for the nuclear facilities. The radioactive waste treatment facility in operation is described, and inspection and maintenance reports of the nuclear facilities prepared for decommissioning are presented. (ln)

  18. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

  19. Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

    Science.gov (United States)

    Zakaria, Norasalwa; Mustafa, Muhammad Khairul Ariff; Anuar, Abul Adli; Idris, Hairul Nizam; Ba'an, Rohyiza

    2014-02-01

    Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future.

  20. Status of the Decommissioning Project Management Information System Development of KAERI in 2015

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Various information systems have been developed and used at decommissioning sites for planning a project, record keeping for a post management and cost estimation. KAERI is the only one expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR-1 and 2 and UCP (Uranium Conversion Plant) decommission. KRR-1 and KRR-2 are TRIGA MARK type of research reactor which were constructed worldwide. Hence, there are many chance to use decommissioning experiences and data when other TRIGA MARK type of research reactors start to decommission. KAERI DPMIS stands for Decommissioning Project Management Information System, which is aiming to re-use of data effectively. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DPMIS application program, which is going to be an important mile stone of decommission industry in Korea. User friendly graphical interface and lots of actual data let people well understood on decommission planning. It is expected that continuous effort and funds will be delivered to this research.

  1. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 5 - FUEL CHANEL DECOMMISSIONING

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2014-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, cost-effective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

  2. An apparatus for studying spallation neutrons in the Aberdeen Tunnel laboratory

    CERN Document Server

    Blyth, S C; Chen, X C; Chu, M C; Hahn, R L; Ho, T H; Hsiung, Y B; Hu, B Z; Kwan, K K; Kwok, M W; Kwok, T; Lau, Y P; Lee, K P; Leung, J K C; Leung, K Y; Lin, G L; Lin, Y C; Luk, K B; Luk, W H; Ngai, H Y; Ngan, S Y; Pun, C S J; Shih, K; Tam, Y H; Tsang, R H M; Wang, C H; Wong, C M; Wong, H L; Wong, H H C; Wong, K K; Yeh, M

    2013-01-01

    In this paper, we describe the design, construction and performance of an apparatus installed in the Aberdeen Tunnel laboratory in Hong Kong for studying spallation neutrons induced by cosmic-ray muons under a vertical rock overburden of 611 meter water equivalent (m.w.e.). The apparatus comprises of six horizontal layers of plastic-scintillator hodoscopes for determining the direction and position of the incident cosmic-ray muons. Sandwiched between the hodoscope planes is a neutron detector filled with 650 kg of liquid scintillator doped with about 0.06% of Gadolinium by weight for improving the e?ciency of detecting the spallation neutrons. Performance of the apparatus is also presented.

  3. Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.

    1983-07-01

    Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

  4. Decommissioning of nuclear facilities in Europe. Status December 2014; Stilllegung kerntechnischer Anlagen in Europa. Stand: Dezember 2014

    Energy Technology Data Exchange (ETDEWEB)

    Brendebach, Boris; Imielski, Przemyslaw [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany); Kuehn, Kerstin; Rehs, Bernd

    2015-05-15

    The report on decommissioning activities of nuclear facilities in Europe (status December 2014) summarizes the reasons and plans for decommissioning, the regulations and responsibilities, the decommissioning strategies and the finalized decommissioning projects. The specific activities are described for Armenia, Belgium, Bulgaria, Denmark, Germany, Estonia, Finland, France, Greece, UK, Italy, Croatia, Latvia, Lithuania, Moldavia, Netherlands, Norway, Austria, Poland, Portugal, Rumania, Russia, Sweden, Switzerland, Serbia, Slovakia, Spain, Czech Republic, Turkey, Ukraine, Hungary and Belarus.

  5. Technology, safety, and costs of decommissioning a reference pressurized water reactor power station. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

    1978-05-01

    Detailed appendices are presented under the following headings: reference PWR facility description, reference PWR site description, estimates of residual radioactivity, alternative methods for financing decommissioning, radiation dose methodology, generic decommissioning activities, intermediate dismantlement activities, safe storage and deferred dismantlement activities, compilation of unit cost factors, and safety assessment details.

  6. Decommissioning of the Astra research reactor: Review and status on July 2003

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2003-01-01

    Full Text Available The paper describes work on the decommissioning of the ASTRA research reactor at the Austrian Research Centers Seibersdorf. Organizational, planning, and dismantling work done until July 2003 including radiation protection and waste management procedures as well as the current status of the project are presented. Completion of the decommissioning activities is planned for 2006.

  7. Study for reducing radioactive solid waste at ITER decommissioning period

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Shinichi; Araki, Masanori; Ohmori, Junji; Ohno, Isamu; Sato, Satoshi; Yamauchi, Michinori; Nishitani, Takeo [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2002-11-01

    It is one of the foremost goals for ITER to demonstrate the attractiveness with regard to safety and environmental potential. This implies that the radioactive materials and waste at decommissioning phase should carefully be treated with prescribed regulations. As possible activities during the Coordinated Technical Activity (CTA), the authors have performed a feasibility study for searching the possibility of effective reduction in the activated level as reasonably achievable as possible by taking account of minimum material changes while keeping original design concept and structure. Major induced activation in ITER comes from activated nickel and cobalt so that it is effective for the major structural components to minimize their material contents. Employing less Ni and Co steel in place of high-Ni austenitic stainless steel for blanket shield block, vacuum vessel shield material and TF coil casing has been considered as one of the effective plans to reduce the activated materials at the decommissioning phase. In this study, two less-Ni austenitic stainless steels are evaluated; one is high-Mn austenitic stainless steel JK2 which is developing for jacket material of ITER CS coil and the other is SS204L/ASTM-XM-11 which is also high-Mn steel specified in the popular standards such as American Society of Testing and Material (ASTM). Based on the material changes, activation analyses have been performed to investigate the possibility of reducing radioactive wastes. As a most impressive result, at 40 years after the termination some of main components such as a TF coil casing will reach to the clearance level which is specified by IAEA, and most components will be categorized into extremely low level waste except for limited components. These results will give the appropriate short decommissioning period that is assumed to start at 100 years after the termination in the original design. (author)

  8. Radiological Characteristics of decommissioning waste from a CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Dong Keun; Choi, Heui Joo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ahmed, Rizwan; Heo, Gyun Young [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

    2011-11-15

    The radiological characteristics for waste classification were assessed for neutron-activated decommissioning wastes from a CANDU reactor. The MCNP/ORIGEN2 code system was used for the source term analysis. The neutron flux and activation cross-section library for each structural component generated by MCNP simulation were used in the radionuclide buildup calculation in ORIGEN2. The specific activities of the relevant radionuclides in the activated metal waste were compared with the specified limits of the specific activities listed in the Korean standard and 10 CFR 61. The time-average full-core model of Wolsong Unit 1 was used as the neutron source for activation of in-core and ex-core structural components. The approximated levels of the neutron flux and cross-section, irradiated fuel composition, and a geometry simplification revealing good reliability in a previous study were used in the source term calculation as well. The results revealed the radioactivity, decay heat, hazard index, mass, and solid volume for the activated decommissioning waste to be 1.04 x 10{sup 16} Bq, 2.09 x 10{sup 3} W, 5.31 x 10{sup 14} m{sup 3}-water, 4.69 x 10{sup 5} kg, and 7.38 x 10{sup 1} m{sup 3}, respectively. According to both Korean and US standards, the activated waste of the pressure tubes, calandria tubes, reactivity devices, and reactivity device supporters was greater than Class C, which should be disposed of in a deep geological disposal repository, whereas the side structural components were classified as low- and intermediate-level waste, which can be disposed of in a land disposal repository. Finally, this study confirmed that, regardless of the cooling time of the waste, 15% of the decommissioning waste cannot be disposed of in a land disposal repository. It is expected that the source terms and waste classification evaluated through this study can be widely used to establish a decommissioning/disposal strategy and fuel cycle analysis for CANDU reactors.

  9. Radiochemical analysis of concrete samples for decommission of nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zapata-Garcia, Daniel; Wershofen, Herbert [Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100 38116, Braunschweig (Germany); Larijani, Cyrus; Sobrino-Petrirena, Maitane; Garcia-Miranda, Maria; Jerome, Simon M. [National Physical Laboratory (NPL), Hampton Road, Teddington, Middlesex, TW11 0LW (United Kingdom)

    2014-07-01

    Decommissioning of the oldest nuclear power reactors are some of the most challenging technological legacy issues many countries will face in forthcoming years, as many power reactors reach the end of their design lives. Decommissioning of nuclear reactors generates large amounts of waste that need to be classified according to their radioactive content. Approximately 10 % of the contaminated material ends up in different repositories (depending on their level of contamination) while the rest is decontaminated, measured and released into the environment or sent for recycling. Such classification needs to be done accurately in order to ensure that both the personnel involved in decommissioning and the population at large are not needlessly exposed to radiation or radioactive material and to minimise the environmental impact of such work. However, too conservative classification strategies should not be applied, in order to make proper use of radioactive waste repositories since space is limited and the full process must be cost-effective. Implicit in decommissioning and classification of waste is the need to analyse large amounts of material which usually combine a complex matrix with a non-homogeneous distribution of the radionuclides. Because the costs involved are large, it is possible to make great savings by the adoption of best available practices, such as the use of validated methods for on-site measurements and simultaneous determination of more than one radionuclide whenever possible. The work we present deals with the development and the validation of a procedure for the simultaneous determination of {sup 241}Am, plutonium isotopes, uranium isotopes and {sup 90}Sr in concrete samples. Samples are firstly ground and fused with LiBO{sub 2} and Li{sub 2}B{sub 4}O{sub 7}. After dissolution of the fused sample, silicate and alkaline elements are removed followed by radiochemical separation of the target radionuclides using extraction chromatography. Measurement

  10. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

  11. Progress in the decommissioning planning for the Kiev’s research reactor WWR-M

    Directory of Open Access Journals (Sweden)

    Lobach Yuri N.

    2010-01-01

    Full Text Available The Kiev’s research reactor WWR-M has been in operation for more than 50 years and its further operation is planned for no less than 8-10 years. The acting nuclear legislation of Ukraine demands from the operator to perform the decommissioning planning during the reactor operation stage as early as possible. Recently, the Decommissioning Program has been approved by the regulatory body. The Program is based on the plans for the further use of the reactor site and foresees the strategy of immediate dismantling. The Program covers the whole de- commissioning process and represents the main guiding document during the whole decommissioning period, which determines and substantiates the principal technical and organizational activities on the preparation and implementation of the reactor decommissioning, the consequence of the decommissioning stages, the sequence of planned works and measures as well as the necessary conditions and infrastructure for the provision and safe implementation.

  12. Pre-decommissioning complex engineering and radiation inspection of the WWR-M reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lobach, Yuri N.; Shevel, Valery N. [NASU, Kiev (Ukraine). Inst. for Nuclear Research

    2014-04-15

    The Kiev's research reactor WWR-M has been in operation for more than 50 years. Decommissioning plan should to be prepared and approved before the beginning of the decommissioning activities. A key activity during reactor operation is implementing the pre-decommissioning complex engineering and radiation inspection. It should be done with objective to collect, arrange and analyze the data related to the engineering and radiation conditions of the reactor systems and equipment. Recently, such an inspection has been completed. The analysis of available documentation has consisted in the assessment of design, construction, technological, assembling, operation, maintenance and repair documentation for each system. The radiation survey was performed in two different ways, namely, by doing the experimental measurements and by performing calculations. The collected data are provided a comprehensive technical basis for the development of decommissioning documentation which is required for the planning and implementation of the reactor decommissioning. (orig.)

  13. Selection of relevant items for decommissioning costing estimation of a PWR using fuzzy logic

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Busse, Alexander Lucas; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: alexlucasb@gmail.com, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

    2015-07-01

    The decommissioning is an important part of a nuclear power plant life cycle which may occur by technical, economical or safety reasons. Decommissioning requires carrying out a large number of tasks that should be planned in advance, involves cost evaluations, preparation of plans of activity and actual operational actions. Despite the large number of tasks, only part of them is relevant for cost estimation purpose. The technical literature and international regulatory agencies suggest a variety of methods for decommissioning cost estimation. Most of them require a very detailed knowledge of the plant and data available suitable for plants that are starting their decommissioning but not for those in the planning stage. The present work aims to apply fuzzy logic to sort out relevant items to cost estimation in order to reduce the work effort involved. The scheme uses parametric equations for specific cost items, and is applied to specific parts of the process of nuclear power plant decommissioning. (author)

  14. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

    2015-07-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  15. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 7 - FUNCTIONING OF THE DECOMMISSIONING DEVICE

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2015-05-01

    Full Text Available The scope of this paper is to achieve the device functioning steps for the commissioning of the horizontal fuel channels of calandria vessel. The dismantling of the fuel channel is performed by one device which shall provide radiation protection during the stages of decommissioning, ensuring radiation protection of the workers. For the decommissioning operation design shall be taken to ensure all aspects of security, environmental protection during decommissioning operation steps and creating and implementing work procedures resulting from developed decommissioning plan. The fuel channel decommissioning device is designed for dismantling and extraction of the fuel channel and its components. The decommissioning operation consists of following major steps: platform with device positioning to the fuel channel to be dismantled; coupling and locking the device at the fuel channel; unblock, extract and store the channel closure plug; unblock, extract and store the channel shield plug; block and cut the middle and the end of the pressure tube; block, extract and store the end fitting; block, extract and store the half of pressure tube; mounting of the extended closing plug. The operations steps are performed by the Cutting and Extraction Device and by the extraction actuator from the device handling elements assembly. After each step of dismantling is necessary the confirmation its finalization in order to perform the next operation step. The dismantling operation steps of the fuel channel components are repeated for all the 380 channels of the reactor, from the front of calandria side (plane R as well as the rear side (plane R'.

  16. Characterisation of radioactive waste products associated with plant decommissioning.

    Science.gov (United States)

    Sejvar, J; Fero, A H; Gil, C; Hagler, R J; Santiago, J L; Holgado, A; Swenson, R

    2005-01-01

    The inventory of radioactivity that must be considered in the decommissioning of a typical 1000 MWe Spanish pressurised water reactor (PWR) was investigated as part of a generic plant decommissioning study. Analyses based on DORT models (in both R-Z and R-theta geometries) were used with representative plant operating history and core power distribution data in defining the expected neutron environment in regions near the reactor core. The activation analyses were performed by multiplying the DORT scalar fluxes by energy-dependent reaction cross sections (based on ENDF/B-VI data) to generate reaction rates on a per atom basis. The results from the ORIGEN2 computer code were also used for determining the activities associated with certain nuclides where multi-group cross section data were not available. In addition to the bulk material activation of equipment and structures near the reactor, the activated corrosion-product (or 'crud') deposits on system and equipment surfaces were considered. The projected activities associated with these sources were primarily based on plant data and experience from operating PWR plants.

  17. Progress on radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark. Center for Nuclear Technologies (NuTech), Roskilde (Denmark))

    2012-01-15

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  18. Decommissioning of the high flux beam reactor at Brookhaven Lab

    Energy Technology Data Exchange (ETDEWEB)

    Hu, J.P. [National Synchrotron Light Source, Brookhaven Laboratory, Upton, NY 11973 (United States); Reciniello, R.N. [Radiological Control Div., Brookhaven Laboratory, Upton, NY 11973 (United States); Holden, N.E. [National Nuclear Data Center, Brookhaven Laboratory, Upton, NY 11973 (United States)

    2011-07-01

    The high-flux beam reactor (HFBR) at the Brookhaven National Laboratory was a heavy water cooled and moderated reactor that achieved criticality on Oct. 31, 1965. It operated at a power level of 40 megawatts. An equipment upgrade in 1982 allowed operations at 60 megawatts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 megawatts. The HFBR was shut down in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of groundwater from wells located adjacent to the reactor's spent fuel pool. The reactor remained shut down for almost three years for safety and environmental reviews. In November 1999 the United States Dept. of Energy decided to permanently shut down the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome, which still contains the irradiated reactor vessel, is presently under 24/7 surveillance for safety. Detailed dosimetry performed for the HFBR decommissioning during 1996-2009 is described in the paper. (authors)

  19. Resource book: Decommissioning of contaminated facilities at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

  20. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  1. On Younger Stakeholders and Decommissioning of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tyszkiewicz, Bogumila; Labor, Bea

    2009-08-15

    In modern democratic countries, information sharing and effective and open communication concerning dismantling and decommissioning of of nuclear facilities as well as the management of nuclear waste are essential for the task to build the confidence required for any further development of nuclear energy. At the same time, it is often perceived that all decision making processes about nuclear energy policies are probably increasingly influenced by public opinion. Nuclear and radiation safety Authorities have a clear role in this regard to provide unbiased information on any health and safety related issues. In order to meet this need, it is necessary for Authorities and others to understand the values and opinions of the citizens, and especially the younger ones. They hold the key to the future at the same time as their perspective on these issues is the least understood. The need of greater public participation in decision making is becoming increasingly recognised the scientific as well as the political community. Many activities are carried out in order to stimulate to higher levels of public involvement in decision making in this active research area. Younger citizens is a stakeholder group that is often excluded in decision- making processes. The existence of large gaps between the involvement of older and younger stakeholders in decision making processes needs to be addressed, since such imbalances might otherwise lead to unequal opportunities between generations and limit the future consumption level of the coming generations. Another demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in line with the environmental and health codex is essential. An appropriate balance in this regard must be

  2. The role of the IAEA in international guidance and assistance on decommissioning of small nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laraia, M., E-mail: m.laraia@iaea.or [IAEA, Wagramerstrasse 5, A-1400 Vienna (Austria)

    2010-10-15

    The IAEA has included decommissioning in its regular programmes since the early 1970 decade. Since 1985, decommissioning has been considered as a separate programme within the IAEA. Decommissioning has become a topic of great interest to many countries because of the large number of facilities that have reached or are nearing the end of their operating lifetime. Until recently, attention was focused on the decommissioning of nuclear power plants, and to less extent, other large nuclear facilities like nuclear fuel cycle facilities. Quite a few countries, however, are now being faced with the decommissioning of research reactors and other small non-reactor facilities, which are prevailing in most of our Member States. This factor demands equal attention in IAEA programmes. Not unlike IAEA publications, most of existing technical literature on decommissioning addresses technological and other aspects in decontamination and dismantling of large nuclear facilities. It should however be noted that most nuclear facilities are smaller -in size and complexity- and may present a lower radiological risk in decommissioning than the larger facilities. Such facilities e.g. small research reactors, critical assemblies, biological and medical laboratories, factories manufacturing radioactive products etc. are often located in countries where decommissioning experience and related resources are often limited. The risk here is that even minimum requirements and strategies be disregarded in decommissioning of these facilities resulting in unnecessary costs, delays, and possible safety concerns in the course of decontamination and dismantling activities. Besides, guidance on decommissioning of larger facilities can be misleading for smaller facilities. This paper provides an update on current and foreseen IAEA activities in the field of decommissioning of small nuclear facilities. Most IAEA activities can be included into the following two categories: drafting technical and safety

  3. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    Energy Technology Data Exchange (ETDEWEB)

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  4. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2000-01-01

    Fundamentals on the plan, the national policy, the safety securities for the life extension of the nuclear power plant was established from the domestic/abroad documents and case studies in relation with the life extension and decommissioning of the nuclear power plant. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the domestic/abroad standard of the decommissioning (decontamination. dismantling) technology and regulation. Moreover, the study on the cost estimation method has been carried out for the decommissioning of the nuclear power plant. (author)

  5. Preliminary decommissioning plan for Clab (Central interim storage for spent fuels); Preliminaer avvecklingsplan foer Clab

    Energy Technology Data Exchange (ETDEWEB)

    Gatter, Patrik; Wikstroem, Nina [SWECO, Stockholm (Sweden); Hallberg, Bengt [Studsvik Nuclear AB, Nykoeping (Sweden)

    2005-12-15

    In the The Swedish Radiation Protection Authority's Regulations SSI FS 2002:04 and The Swedish Nuclear Power Inspectorate's Regulations SKI FS 2004:1 it is stated that the owner of a nuclear facility must have a preliminary plan for decommissioning of the plant. The present report is a preliminary plan for decommissioning the Central interim storage for spent fuels (Clab). Clab will be decommissioned when all spent fuels and reactor core components have been sent to final disposal. The time for the decommissioning is dependent on the time for phasing out the last Swedish nuclear reactor. At present it is thought that Clab will remain in operation until after year 2050. During the work with this project, nothing has been found that indicates that decommissioning Clab could be more complicated than other plants whose decommissioning is closer in time. On the contrary, smaller radiation doses to the personnel are expected, as well as limited amounts of low and medium activity waste. This plan will be updated and more detailed as the time for decommissioning approaches.

  6. Decontamination and decommissioning technology tree and the current status of the technologies

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Won, H.J.; Kim, G.N.; Lee, K.W.; Chol, W.K.; Jung, C.H.; Kim, C.J.; Kim, S.H.; Kwon, S.O.; Chung, C.M

    2001-03-01

    A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point.

  7. On Younger Stakeholders and Decommissioning of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tyszkiewicz, Bogumila; Labor, Bea

    2009-08-15

    In modern democratic countries, information sharing and effective and open communication concerning dismantling and decommissioning of of nuclear facilities as well as the management of nuclear waste are essential for the task to build the confidence required for any further development of nuclear energy. At the same time, it is often perceived that all decision making processes about nuclear energy policies are probably increasingly influenced by public opinion. Nuclear and radiation safety Authorities have a clear role in this regard to provide unbiased information on any health and safety related issues. In order to meet this need, it is necessary for Authorities and others to understand the values and opinions of the citizens, and especially the younger ones. They hold the key to the future at the same time as their perspective on these issues is the least understood. The need of greater public participation in decision making is becoming increasingly recognised the scientific as well as the political community. Many activities are carried out in order to stimulate to higher levels of public involvement in decision making in this active research area. Younger citizens is a stakeholder group that is often excluded in decision- making processes. The existence of large gaps between the involvement of older and younger stakeholders in decision making processes needs to be addressed, since such imbalances might otherwise lead to unequal opportunities between generations and limit the future consumption level of the coming generations. Another demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in line with the environmental and health codex is essential. An appropriate balance in this regard must be

  8. Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

    Science.gov (United States)

    Kaiser, Mark J

    2015-08-01

    Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed.

  9. A Prediction on the Unit Cost Estimation for Decommissioning Activities Using the Experienced Data from DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Kook; Park, Hee Seong; Choi, Yoon Dong; Song, Chan Ho; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The KAERI (Korea Atomic Energy Research Institute) has developed the DECOMMIS (Decommissioning Information Management System) and have been applied for the decommissioning project of the KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant), as the meaning of the first decommissioning project in Korea. All information and data which are from the decommissioning activities are input, saved, output and managed in the DECOMMIS. This system was consists of the web server and the database server. The users could be access through a web page, depending on the input, processing and output, and be modified the permissions to do such activities can after the decommissioning activities have created the initial system-wide data is stored. When it could be used the experienced data from DECOMMIS, the cost estimation on the new facilities for the decommissioning planning will be established with the basic frame of the WBS structures and its codes. In this paper, the prediction on the cost estimation through using the experienced data which were store in DECOMMIS was studied. For the new decommissioning project on the nuclear facilities in the future, through this paper, the cost estimation for the decommissioning using the experienced data which were WBS codes, unit-work productivity factors and annual governmental unit labor cost is proposed. These data were from the KRR and UCP decommissioning project. The differences on the WBS code sectors and facility characterization between new objected components and experienced dismantled components was reduces as scaling factors. The study on the establishment the scaling factors and cost prediction for the cost estimation is developing with the algorithms from the productivity data, now.

  10. Environmental geophysics at the Southern Bush River Peninsula, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Davies, B.E.; Miller, S.F.; McGinnis, L.D. [and others

    1995-05-01

    Geophysical studies have been conducted at five sites in the southern Bush River Peninsula in the Edgewood Area of Aberdeen Proving Ground, Maryland. The goals of the studies were to identify areas containing buried metallic objects and to provide diagnostic signatures of the hydrogeologic framework of the site. These studies indicate that, during the Pleistocene Epoch, alternating stands of high and low sea level resulted in a complex pattern of channel-fill deposits. Paleochannels of various sizes and orientations have been mapped throughout the study area by means of ground-penetrating radar and EM-31 techniques. The EM-31 paleochannel signatures are represented onshore either by conductivity highs or lows, depending on the depths and facies of the fill sequences. A companion study shows the features as conductivity highs where they extend offshore. This erosional and depositional system is environmentally significant because of the role it plays in the shallow groundwater flow regime beneath the site. Magnetic and electromagnetic anomalies outline surficial and buried debris throughout the areas surveyed. On the basis of geophysical measurements, large-scale (i.e., tens of feet) landfilling has not been found in the southern Bush River Peninsula, though smaller-scale dumping of metallic debris and/or munitions cannot be ruled out.

  11. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Remedial investigation results

    Energy Technology Data Exchange (ETDEWEB)

    Yuen, C. R.; Martino, L. E.; Biang, R. P.; Chang, Y. S.; Dolak, D.; Van Lonkhuyzen, R. A.; Patton, T. L.; Prasad, S.; Quinn, J.; Rosenblatt, D. H.; Vercellone, J.; Wang, Y. Y.

    2000-03-14

    This report presents the results of the remedial investigation (RI) conducted at J-Field in the Edgewood Area of Aberdeen Proving Ground (APG), a U.S. Army installation located in Harford County, Maryland. Since 1917, activities in the Edgewood Area have included the development, manufacture, and testing of chemical agents and munitions and the subsequent destruction of these materials at J-Field by open burning and open detonation. These activities have raised concerns about environmental contamination at J-Field. This RI was conducted by the Environmental Conservation and Restoration Division, Directorate of Safety, Health and Environmental Division of APG, pursuant to requirements outlined under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). The RI was accomplished according to the procedures developed by the U.S. Environmental Protection Agency (EPA 1988). The RI provides a comprehensive evaluation of the site conditions, nature of contaminants present, extent of contamination, potential release mechanisms and migration pathways, affected populations, and risks to human health and the environment. This information will be used as the basis for the design and implementation of remedial actions to be performed during the remedial action phase, which will follow the feasibility study (FS) for J-Field.

  12. Natural attenuation of chlorinated volatile organic compounds in a freshwater tidal wetland, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Lorah, Michelle M.; Olsen, Lisa D.; Smith, Barrett L.; Johnson, Mark A.; Fleck, William B.

    1997-01-01

    Ground-water contaminant plumes that are flowing toward or currently discharging to wetland areas present unique remediation problems because of the hydrologic connections between ground water and surface water and the sensitive habitats in wetlands. Because wetlands typically have a large diversity of microorganisms and redox conditions that could enhance biodegradation, they are ideal environments for natural attenuation of organic contaminants, which is a treatment method that would leave the ecosystem largely undisturbed and be cost effective. During 1992-97, the U.S. Geological Survey investigated the natural attenuation of chlorinated volatile organic compounds (VOC's) in a contaminant plume that discharges from a sand aquifer to a freshwater tidal wetland along the West Branch Canal Creek at Aberdeen Proving Ground, Maryland. Characterization of the hydrogeology and geochemistry along flowpaths in the wetland area and determination of the occurrence and rates of biodegradation and sorption show that natural attenuation could be a feasible remediation method for the contaminant plume that extends along the West Branch Canal Creek.

  13. Hydrogeology and soil gas at J-Field, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Hughes, W.B.

    1993-01-01

    Disposal of chemical warfare agents, munitions, and industrial chemicals in J-Field, Aberdeen Proving Ground, Maryland, has contaminated soil, groundwater and surface water. Seven exploratory borings and 38 observation wells were drilled to define the hydrogeologic framework at J-Field and to determine the type, extent, and movement of contaminants. The geologic units beneath J-Field consist of Coastal Plain sediments of the Cretaceous Patapsco Formation and Pleistocene Talbot Formation. The Patapsco Formation contains several laterally discontinuous aquifers and confining units. The Pleistocene deposits were divided into 3 hydrogeologic units--a surficial aquifer, a confining unit, and a confined aquifer. Water in the surficial aquifer flows laterally from topographically high areas to discharge areas in marshes and streams, and vertically to the underlying confined aquifer. In offshore areas, water flows from the deeper confined aquifers upward toward discharge areas in the Gunpowder River and Chesapeake Bay. Analyses of soil-gas samples showed high relative-flux values of chlorinated solvents, phthalates, and hydrocarbons at the toxic-materials disposal area, white-phosphorus disposal area, and riot-control-agent disposal area. The highest flux values were located downgradient of the toxic materials and white phosphorus disposal areas, indicating that groundwater contaminants are moving from source areas beneath the disposal pits toward discharge points in the marshes and estuaries. Elevated relative-flux values were measured upgradient and downgradient of the riot-control agent disposal area, and possibly result from soil and (or) groundwater contamination.

  14. Hydrogeologic and chemical data for the O-Field area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Nemoff, P.R.; Vroblesky, D.A.

    1989-01-01

    O-Field, located at the Edgewood area of Aberdeen Proving Ground , Maryland, was periodically used for disposal of munitions, waste chemicals, and chemical-warfare agents from World War II through the 1950' s. This report includes various physical, geologic, chemical, and hydrologic data obtained from well-core, groundwater, surface water, and bottom-sediment sampling sites at and near the O-Field disposal area. The data are presented in tables and hydrographs. Three site-location maps are also included. Well-core data include lithologic logs for 11 well- cluster sites, grain-size distributions, various chemical characteristics, and confining unit characteristics. Groundwater data include groundwater chemistry, method blanks for volatile organic carbon, available data on volatile and base/neutral organics, and compilation of corresponding method blanks, chemical-warfare agents, explosive-related products, radionuclides, herbicides, and groundwater levels. Surface-water data include field-measured characteristics; concentrations of various inorganic constituents including arsenic; selected organic constituents with method blanks; detection limits of organics; and a compilation of information on corresponding acids, volatiles, and semivolatiles. Bottom- sediment data include inorganic properties and constituents; organic chemistry; detection limits for organic chemicals; a compilation of information on acids, volatiles, and semivolatiles; and method blanks corresponding to acids, volatiles, and semivolatiles. A set of 15 water- level hydrographs for the period March 1986 through September 1987 also is included in the report. (USGS)

  15. Review of analytical results from the proposed agent disposal facility site, Aberdeen Proving Ground

    Energy Technology Data Exchange (ETDEWEB)

    Brubaker, K.L.; Reed, L.L.; Myers, S.W.; Shepard, L.T.; Sydelko, T.G.

    1997-09-01

    Argonne National Laboratory reviewed the analytical results from 57 composite soil samples collected in the Bush River area of Aberdeen Proving Ground, Maryland. A suite of 16 analytical tests involving 11 different SW-846 methods was used to detect a wide range of organic and inorganic contaminants. One method (BTEX) was considered redundant, and two {open_quotes}single-number{close_quotes} methods (TPH and TOX) were found to lack the required specificity to yield unambiguous results, especially in a preliminary investigation. Volatile analytes detected at the site include 1, 1,2,2-tetrachloroethane, trichloroethylene, and tetrachloroethylene, all of which probably represent residual site contamination from past activities. Other volatile analytes detected include toluene, tridecane, methylene chloride, and trichlorofluoromethane. These compounds are probably not associated with site contamination but likely represent cross-contamination or, in the case of tridecane, a naturally occurring material. Semivolatile analytes detected include three different phthalates and low part-per-billion amounts of the pesticide DDT and its degradation product DDE. The pesticide could represent residual site contamination from past activities, and the phthalates are likely due, in part, to cross-contamination during sample handling. A number of high-molecular-weight hydrocarbons and hydrocarbon derivatives were detected and were probably naturally occurring compounds. 4 refs., 1 fig., 8 tabs.

  16. Contamination source review for Building E1489, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Billmark, K.A.; Hayes, D.C.; Draugelis, A.K. [and others

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E1489 at the Aberdeen Proving Ground (APG) in Maryland. This report may be used to assist the U.S. Army-in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, and geophysical investigation. The field investigations were performed in 1994-1995. Building E1489 located in J-Field on the Gunpowder Peninsula in APG`s Edgewood Area housed a power generator that supplied electricity to a nearby observation tower. Building E1489 and the generator were abandoned in 1974, demolished by APG personnel and removed from real estate records. A physical inspection and photographic documentation of Building E1489 were completed by ANL staff during November 1994. In 1994, ANL staff conducted geophysical surveys in the immediate vicinity of Building E1489 by using several nonintrusive methods. Survey results suggest the presence of some underground objects near Building E1489, but they do not provide conclusive evidence of the source of geophysical anomalies observed during the survey. No air monitoring was conducted at the site, and no information on underground storage tanks associated with Building E1489 was available.

  17. Contamination source review for Building E6891, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Zellmer, S.D.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of various APG buildings. This report provides the results of the contamination source review for Building E6891. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. This building is part of the Lauderick Creek Concrete Slab Test Site, located in the Lauderick Creek Area in the Edgewood Area. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances the potential exists` for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

  18. Contamination source review for Building E3180, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Zellmer, S.D.; Smits, M.P.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E3180 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, collection of air samples, and review of available records regarding underground storage tanks associated with Building E3180. The field investigations were performed by ANL during 1994. Building,E3180 (current APG designation) is located near the eastern end of Kings Creek Road, north of Kings Creek, and about 0.5 miles east of the airstrip within APG`s Edgewood Area. The building was constructed in 1944 as a facsimile of a Japanese pillbox and used for the development of flame weapons systems until 1957 (EAI Corporation 1989). The building was not used from 1957 until 1965, when it was converted and used as a flame and incendiary laboratory. During the 1970s, the building was converted to a machine (metal) shop and used for that purpose until 1988.

  19. Contamination source review for Building E2370, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    O`Reilly, D.P.; Glennon, M.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, and geophysical investigation. This report provides the results of the contamination source review for Building E2370. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances, the potential exists for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

  20. Contamination source review for Building E3162, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Miller, G.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review for Building E3162 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. The field investigations were performed by ANL during 1994 and 1995. Building E3162 (APG designation) is part of the Medical Research Laboratories Building E3160 Complex. This research laboratory complex is located west of Kings Creek, east of the airfield and Ricketts Point Road, and south of Kings Creek Road in the Edgewood Area of APG. The original structures in the E3160 Complex were constructed during World War 2. The complex was originally used as a medical research laboratory. Much of the research involved wound assessment involving chemical warfare agents. Building E3162 was used as a holding and study area for animals involved in non-agent burns. The building was constructed in 1952, placed on inactive status in 1983, and remains unoccupied. Analytical results from these air samples revealed no distinguishable difference in hydrocarbon and chlorinated solvent levels between the two background samples and the sample taken inside Building E3162.

  1. TWRS privatization: Phase I monitoring well engineering study and decommissioning plan

    Energy Technology Data Exchange (ETDEWEB)

    Williams, B.A.

    1996-09-11

    This engineering study evaluates all well owners and users, the status or intended use of each well, regulatory programs, and any future well needs or special purpose use for wells within the TWRS Privatization Phase I demonstration area. Based on the evaluation, the study recommends retaining 11 of the 21 total wells within the demonstration area and decommissioning four wells prior to construction activities per the Well Decommissioning Plan (WHC-SD-EN-AP-161, Rev. 0, Appendix I). Six wells were previously decommissioned.

  2. Revised cost estimate for the decommissioning of the reactor DR3

    DEFF Research Database (Denmark)

    2001-01-01

    The report describes a revision of the cost estimate for the decommissioning of the research Reactor DR 3 as described in the report Risø-R-1250(EN). Decommissioning of the Nuclear Facilities at Risø National Laboratory. Edited by Kurt Lauridsen. Therevision has been performed by the planning group...... in the Risø Decommissioning Department, and has been carried out as a discussion and evaluation of procedures methods and necessary resources to overcome the different phases of the the decommissioningtask of the Reactor....

  3. Sensor Network Demonstration for In Situ Decommissioning - 13332

    Energy Technology Data Exchange (ETDEWEB)

    Lagos, L.; Varona, J.; Awwad, A. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States); Rivera, J.; McGill, J. [Department of Energy - DOE, Environmental Management Office (United States)

    2013-07-01

    Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensor systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to

  4. Long term commitments concerning decommissioning and waste management. French perspective

    Energy Technology Data Exchange (ETDEWEB)

    Milliat, Charles [EDF/CIDEN, 35/37, rue Louis-Guerin, BP 1212, 69611 Villeurbanne Cedex (France); Decobert, Guy [COGEMA/AREVA, 1 rue des Herons BP 302, Montigny-le-Bretonneux 78054 Saint Quentin en Yvelines (France); Pochon, Etienne [CEA/DEN/DPA, Centre de Saclay 91191 Gif sur Yvette Cedex (France)

    2006-07-01

    The majority of France decommissioning activities is occurring in two sectors: the civilian nuclear facilities and the nuclear facilities dedicated to deterrent. In France there are four major civilian operators: EDF (Electricite de France), AREVA, CEA (Commissariat a l'Energie Atomique) and ANDRA (Agence Nationale pour les Dechets Radioactifs). Nuclear energy provides France nearly 80% of its electricity. Presently there are 58 EDF's operating nuclear power plants (PWR), all the gas cooled graphite nuclear power plant (6 units) have been definitively shutdown as well as Superphenix, a fast breeder reactor. The fuel cycle industry belongs to AREVA which is operating all the industrial installations from uranium ore prospecting and mining till used fuel reprocessing. In France, most of the nuclear R and D installations belong to the CEA. Many installations have already been dismantled, are presently being dismantled or are on a waiting list (research reactors, laboratories, pilot plant, etc). ANDRA is in charge since 1991 of the studies and the operation of waste disposal centres (LLW, MLW, HLW and VLLW). The first repository for waste containing short lived radio nuclides (CM, Centre de la Manche) has been closed in 1994 after 25 years of operation, more of 530 000 m{sup 3} have been disposed, the Aube centre (CA) comes into operation in 1991 and has a capacity of 1 000 000 m{sup 3}, ANDRA has opened a disposal for very low level waste (VLLW), close to the Aube centre, in september 2003. The contents of the paper is as follows: I. Current status; II. National policy; III. Decommissioning technique and Inspection; IV. Radioactive waste management; V. Organisations and responsibilities; VI. Funding; VII. Competent bodies.

  5. Heterose sobre os pesos de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos Heterosis upon weights in Canchim and Aberdeen Angus calves and in their reciprocal crosses

    OpenAIRE

    DANIEL PEROTTO; ANTONIO CARLOS CUBAS; JOSÉ LUIZ MOLETTA; CARLOS LESSKIU

    2000-01-01

    O trabalho foi conduzido para estimar a heterose sobre os pesos ao nascimento (PNT), à desmama (P210) e ao ano (P365) e sobre os ganhos de pesos médios diários do nascimento à desmama (G210) e da desmama ao ano (G365) nas quatro primeiras gerações do sistema de cruzamentos alternados entre as raças Canchim (C) e Aberdeen Angus (A). Os dados de 1.147 bezerros nascidos de 1981 a 1998 foram analisados pelo método dos mínimos quadrados, ajustando-se um modelo linear que incluiu os efeitos linear ...

  6. Development of the scenario-based training system to reduce hazards and prevent accidents during decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, KwanSeong; Choi, Jong-Won; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Kang, ShinYoung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Decommissioning of nuclear facilities has to be accomplished by assuring the safety of workers. Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities. In the end, the safety during decommissioning of nuclear facilities will be guaranteed under the principle of ALARA.

  7. 76 FR 8785 - ABB Inc.; License Amendment Request for Decommissioning of the ABB Inc., Combustion Engineering...

    Science.gov (United States)

    2011-02-15

    ... specific DCGLs for Th- 232 and Ra-226. The revised decommissioning plan also includes a description of... NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to...

  8. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  9. 75 FR 54363 - BOEMRE Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Science.gov (United States)

    2010-09-07

    ... information. SUPPLEMENTARY INFORMATION: Title: 30 CFR 250, subpart Q, Decommissioning Activities. OMB Control... prevent or minimize the likelihood of blowouts, loss of well control, fires, spillages, physical... equipment and subsea protective covering; or other departures. Subtotal 50 responses 150...

  10. Decommissioning in Germany. Current status and perspectives; Stilllegung in Deutschland. Status und Perspektiven

    Energy Technology Data Exchange (ETDEWEB)

    Weis, Michael [VGB Power Tech, Essen (Germany)

    2012-11-01

    In 2011 the German government decided as consequence of the Fukushima accident nuclear phase-out. Eight nuclear power plants were shut down, the operating license was withdrawn, nine nuclear power plants are still operated but have a defined shut-down schedule. In view of the NPP companies this decision is contrary to law, the first constitutional complaints were submitted. The decommissioning has not been planned since shortly before lifetime extension has been agreed by the government. A reference concept for the decommissioning and dismantling of nuclear power plants has been developed during the past, the decommissioning and dismantling technology is no more a challenge. The real challenge is the organization of the decommissioning of many plants at the same time, since manpower in the plants, but also in the authorities has to be increased.

  11. Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Elder, H. K.

    1981-10-01

    Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0

  12. Estimating Radon Flux and Environmental Radiation Dose from Decommissioning Uranium Mill Tailings and Mining Debris

    Institute of Scientific and Technical Information of China (English)

    1998-01-01

    Based on a case study on uranium mine No.765 of China National Nuclear Corporation (CNNC), the paper briefly describes disposal program and effect of decommissioning uranium mine/mill facilities and quantitatively evaluates radon fluxes and doses to man of gaseous airborne pathway from mill tailings and mining debris before and after decommissioning, including annual individual effective dose to critical groups and annual collective effective dose to the population within 80 km region of the facilities.

  13. Nuclear reactor decommissioning. (Latest citations from the NTIS bibliographic database). Published Search

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    The bibliography contains citations concerning nuclear power and research reactor decommissioning and decontamination plans, costs, and safety standards. References discuss the design and evaluation of protective confinement, entombment, and dismantling systems. Topics include decommissioning regulations and rules, public and occupational radiation exposure estimates, comparative evaluation, and reactor performance under high neutron flux conditions. Waste packaging and disposal, environmental compliance, and public opinion are examined. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  14. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem.

  15. SGDes project. Decommissioning management system of Enresa; Proyecto SGDes. Sistema de Gestion de Desmantelamiento de Enresa

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez Lopez, M.; Julian, A. de

    2013-03-01

    ENRESA, the public company responsible for managing radioactive waste produced in spain and nuclear facilities decommissioning work, has developed a management information system (SGDes) for the decommissioning of nuclear power plants, critical for the company. SGDes system is capable of responding to operational needs for efficient, controlled and secure way. Dismantling activities require a rigorous operations control within highly specialized, process systematization and safety framework, both the human and technological point of view. (Author)

  16. Engineering Evaluation/Cost Analysis for Decommissioning of the Engineering Test Reactor Complex

    Energy Technology Data Exchange (ETDEWEB)

    A. B. Culp

    2006-10-01

    Preparation of this Engineering Evaluation/Cost Analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, which establishes the Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA) process as an approach for decommissioning.

  17. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

  18. Heterose sobre os pesos de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos

    OpenAIRE

    PEROTTO DANIEL; CUBAS ANTONIO CARLOS; MOLETTA JOSÉ LUIZ; LESSKIU CARLOS

    2000-01-01

    O trabalho foi conduzido para estimar a heterose sobre os pesos ao nascimento (PNT), à desmama (P210) e ao ano (P365) e sobre os ganhos de pesos médios diários do nascimento à desmama (G210) e da desmama ao ano (G365) nas quatro primeiras gerações do sistema de cruzamentos alternados entre as raças Canchim (C) e Aberdeen Angus (A). Os dados de 1.147 bezerros nascidos de 1981 a 1998 foram analisados pelo método dos mínimos quadrados, ajustando-se um modelo linear que incluiu os efeitos linear ...

  19. Hydrogeologic, soil, and water-quality data for j-field, Aberdeen Proving Ground, Maryland, 1989-94

    Science.gov (United States)

    Phelan, D.J.

    1996-01-01

    Disposal of chemical-warfare agents, munitions, and industrial chemicals in J-Field, Aberdeen Proving Ground, Maryland, has resulted in ground-water, surface-water, and soil contamination. This report presents data collected by the U.S. Geological Survey from Novembr 1989 through September 1994 as part of a remedial investigation of J-Field in response to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Hydrogeologic data, soil-gas and soil-quality data, and water-qualtiy data are included.

  20. Contamination source review for Building E5032, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Booher, M.N.; O`Reilly, D.P.; Smits, M.P. [and others

    1995-09-01

    This report by Argonne National Laboratory (ANL) documents results of a contamination source review of Building E5032 at the Aberdeen Proving Ground (APG) in Maryland. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and review of available records regarding underground storage tanks associated with Building E5032. The field investigations were performed by ANL during 1994 and 1995. Building E5032 (APG designation), originally known as Building 99, is located at the northwest comer of the intersection of Hoadley Road and Magnolia Road in the Edgewood Area of APG. It was constructed during World War I as an incendiary bomb filling plant and in 1920s and 1930s maintained as a filling facility. During World War II the building was a pilot plant for the development of a dry white phosphorus filling process. Since then the building has been used for white phosphorus filling pilot studies. Most of the dry filling methods were developed in Building E5032 between 1965 and 1970. Other filling operations in Building E5032 have included mustard during the period shortly after World War II and triethyl aluminum (TEA) during the late 1960s and early 1970s. During the World War II period, the building was connected to the sanitary sewer system with one large and at least one small interior sump. There are also seven sumps adjacent to the exterior of the building: two on the west elevation, four near the four bays on the south elevation, and one at the northeast corner of the building. All of these sumps are connected with the chemical sewer system and received most, if not all, of the production operation wastewater. The discharge from this system was released into the east branch of Canal Creek; the discharge pipe was located southeast of Building E5032. There are no records indicating the use of Building E5032 after 1974, and it is assumed that the building has been out of service since that time.

  1. Molecular Characterization of Salmonella enterica Serovar Aberdeen Negative for H2S Production in China.

    Science.gov (United States)

    Wu, Fuli; Xu, Xuebin; Xie, Jing; Yi, Shengjie; Wang, Jian; Yang, Xiaoxia; Yang, Chaojie; Liang, Beibei; Ma, Qiuxia; Li, Hao; Song, Hongbin; Qiu, Shaofu

    2016-01-01

    Salmonella enterica infections continue to be a significant burden on public health worldwide. The ability of S. enterica to produce hydrogen sulfide (H2S) is an important phenotypic characteristic used to screen and identify Salmonella with selective medium; however, H2S-negative Salmonella have recently emerged. In this study, the H2S phenotype of Salmonella isolates was confirmed, and the selected isolates were subjected to antimicrobial susceptibility testing and molecular identification by multilocus sequence typing, pulsed-field gel electrophoresis, and clustered regularly interspaced short palindromic repeat (CRISPR) analysis. The phs genetic operon was also analyzed. A total of 160 S. enterica serovar Aberdeen isolates were detected between 2005 and 2013 in China. Of them, seven non-H2S-producing isolates were detected. Notably, four samples yielded four pairs of isolates with different H2S phenotypes, simultaneously. The data demonstrated that H2S-negative isolates were genetically closely related to H2S-positive isolates. Three new spacers (Abe1, Abe2, and Abe3) were identified in CRISPR locus 1 in four pairs of isolates with different H2S phenotypes from the same samples. Sequence analysis revealed a new nonsense mutation at position 208 in the phsA gene of all non-H2S-producing isolates. Additionally, we describe a new screening procedure to avoid H2S-negative Salmonella, which would normally be overlooked during laboratory and hospital screening. The prevalence of this pathogen may be underestimated; therefore, it is important to focus on improving surveillance of this organism to control its spread.

  2. Potential health impacts from range fires at Aberdeen Proving Ground, Maryland.

    Energy Technology Data Exchange (ETDEWEB)

    Willians, G.P.; Hermes, A.M.; Policastro, A.J.; Hartmann, H.M.; Tomasko, D.

    1998-03-01

    This study uses atmospheric dispersion computer models to evaluate the potential for human health impacts from exposure to contaminants that could be dispersed by fires on the testing ranges at Aberdeen Proving Ground, Maryland. It was designed as a screening study and does not estimate actual human health risks. Considered are five contaminants possibly present in the soil and vegetation from past human activities at APG--lead, arsenic, trichloroethylene (TCE), depleted uranium (DU), and dichlorodiphenyltrichloroethane (DDT); and two chemical warfare agents that could be released from unexploded ordnance rounds heated in a range fire--mustard and phosgene. For comparison, dispersion of two naturally occurring compounds that could be released by burning of uncontaminated vegetation--vinyl acetate and 2-furaldehyde--is also examined. Data from previous studies on soil contamination at APG are used in conjunction with conservative estimates about plant uptake of contaminants, atmospheric conditions, and size and frequency of range fires at APG to estimate dispersion and possible human exposure. The results are compared with US Environmental Protection Agency action levels. The comparisons indicate that for all of the anthropogenic contaminants except arsenic and mustard, exposure levels would be at least an order of magnitude lower than the corresponding action levels. Because of the compoundingly conservative nature of the assumptions made, they conclude that the potential for significant human health risks from range fires is low. The authors recommend that future efforts be directed at fire management and control, rather than at conducting additional studies to more accurately estimate actual human health risk from range fires.

  3. Work plan for conducting an ecological risk assessment at J-Field, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Hlohowskyj, I.; Hayse, J.; Kuperman, R. [Argonne National Lab., IL (United States). Environmental Assessment Div.] [and others

    1995-03-01

    The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland, and activities at the Edgewood Area since World War II have included the development, manufacture, testing, and destruction of chemical agents and munitions. The J-Field site was used to destroy chemical agents and munitions by open burning and open detonation. This work plan presents the approach proposed to conduct an ecological risk assessment (ERA) as part of the RI/FS program at J-Field. This work plan identifies the locations and types of field studies proposed for each area of concern (AOC), the laboratory studies proposed to evaluate toxicity of media, and the methodology to be used in estimating doses to ecological receptors and discusses the approach that will be used to estimate and evaluate ecological risks at J-Field. Eight AOCs have been identified at J-Field, and the proposed ERA is designed to evaluate the potential for adverse impacts to ecological receptors from contaminated media at each AOC, as well as over the entire J-Field site. The proposed ERA approach consists of three major phases, incorporating field and laboratory studies as well as modeling. Phase 1 includes biotic surveys of the aquatic and terrestrial habitats, biological tissue sampling and analysis, and media toxicity testing at each AOC and appropriate reference locations. Phase 2 includes definitive toxicity testing of media from areas of known or suspected contamination or of media for which the Phase 1 results indicate toxicity or adverse ecological effects. In Phase 3, the uptake models initially developed in Phase 2 will be finalized, and contaminant dose to each receptor from all complete pathways will be estimated.

  4. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Harris, P.W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

    2001-07-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  5. Application of Robotics in Decommissioning and Decontamination - 12536

    Energy Technology Data Exchange (ETDEWEB)

    Banford, Anthony; Kuo, Jeffrey A. [National Nuclear Laboratory, Risley, Warrington (United Kingdom); Bowen, R.A. [National Nuclear Laboratory, Sellafield, Cumbria (United Kingdom); Szilagyi, Andrew; Kirk, Paula [U.S. Department of Energy, Washington, D.C. (United States)

    2012-07-01

    Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure. However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better

  6. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  7. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  8. A State of the Art on the Technology for Recycling and Reuse of the Decommissioning Concrete Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Chung Hun; Choi, Wang Kyu; Min, Byung Youn; Oh, Won Zin; Lee, Kun Woo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-02-15

    This report describes the reduction and recycling technology of decommissioning concrete waste. Decontamination and decommissioning (D and D) becomes one of the most important nuclear markets especially in the developed countries including USA, UK and France where lots of the retired nuclear facilities have been waiting for decommissioning. In our country the KAERI has been carrying out the decommissioning of the retired TRIGA MARK II and III research reactors and an uranium conversion plant as the first national decommissioning project since 1998. One of the most important areas of the decommissioning is a management of a huge amount of a decommissioning waste the cost of which is more than half of the total decommissioning cost. Therefore reduction in decommissioning waste by a reuse or a recycle is an important subject of decommissioning technology development in the world. Recently much countries pay attention to recycle the large amount of concrete dismantling waste resulted from both a nuclear and a non nuclear industries. In our country, much attention was taken in a recycle of concrete dismantling waste as a concrete aggregate, but a little success has been resulted due to the disadvantages such as a weakness of hardness and surface mortar contamination. A recycle in nuclear industry and a self disposal of the radioactively contaminated concrete wastes are main directions of concrete wastes resulted from a nuclear facility decommissioning. In this report it was reviewed the state of art of the related technologies for a reduction and a recycle of concrete wastes from a nuclear decommissioning in the country and abroad. Prior to recycle and reuse in the nuclear sector, however, the regulatory criteria for the recycle and reuse of concrete waste should be established in parallel with the development of the recycling technology.

  9. Intelligence, Social Class of Origin, Childhood Behavior Disturbance and Education as Predictors of Status Attainment in Midlife in Men: The Aberdeen Children of the 1950s Study

    Science.gov (United States)

    von Stumm, Sophie; Macintyre, Sally; Batty, David G.; Clark, Heather; Deary, Ian J.

    2010-01-01

    In a birth cohort of 6281 men from Aberdeen, Scotland, social class of origin, childhood intelligence, childhood behavior disturbance and education were examined as predictors of status attainment in midlife (46 to 51 years). Social class of origin, intelligence and behavior disturbance were conceptualized as correlated predictors, whose effects…

  10. Decommissioning analysis of the scrapers in the NSRL Linac using depth profiling

    Institute of Scientific and Technical Information of China (English)

    何丽娟; 李裕熊; 李为民; 陈裕凯; 任广益

    2015-01-01

    For a high-energy electron facility, estimates of induced radioactivity in materials are of considerable impor-tance to ensure that the exposure of personnel and the environment remains as low as reasonably achievable. In addition, accurate predictions of induced radioactivity are essential to the design, operation, and decommission-ing of a high-energy electron linear accelerator. In the case of the 200-MeV electron linac of the National Syn-chrotron Radiation Laboratory (NSRL), the electrons are accelerated by five acceleration tubes and collimated by copper scrapers. The scrapers, which play a vital role in protecting the acceleration cavity, are bombarded by many electrons over a long-term operation, which causes a significant amount of induced radioactivity. Re-cently, the NSRL Linac is the first high-energy electron linear accelerator in China to be out of commission. Its decommissioning is highly significant for obtaining decommissioning experience. This paper focuses on the measurement of induced radioactivity on the fourth scraper, where the electron energy was 158 MeV. The radionuclides were classified according to their half-lives. Such a classification provides a reliable basis for the formulation of radiation protection and facility decommissioning. To determine the high-radioactivity area and to facilitate the decommissioning process, the slicing method was applied in this study. The specific activity of 60Co in each slice was measured at a cooling time of ten months, and the results were compared with the predictions generated by Monte Carlo program FLUKA. The trend of the measured results is in good agreement with the normalized simulation results. The slicing simulation using Monte Carlo method is useful for the de-termination of high-radiation areas and proper material handling protocols and, therefore, lays a foundation for the accumulation of decommissioning experience.

  11. Aagesta-BR3 Decommissioning Cost. Comparison and Benchmarking Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff [NAC International, Henley on Thames (United Kingdom)

    2002-11-01

    This report presents the results of decommissioning cost analyses focusing on discrete working packages within the decommissioning program of the BR3 reactor in Mol, Belgium and comparison of them with cost estimate data for the Aagesta research reactor in Sweden. The specific BR3 work packages analysed were: Primary coolant piping decontamination; Primary coolant piping dismantling; Vulcain reactor internals dismantling; Westinghouse reactor internals dismantling; Reactor vessel dismantling. The main conclusions to be drawn from the analyses are that: The fixed costs related to decontamination and dismantling activities generally are a very important part of the overall resources needed to execute the work, with the Reactor Pressure Vessel (RPV) seemingly being significantly more demanding than other major components. Cutting activities tend to need something like 150 to 200 labour hours per m{sup 2} of reactor equipment dismantled. Fixed investment costs to set up the equipment needed to cut up major vessels or internals appear to be in the range of MSEK 4 to 8. Consumables costs vary according to the nature of the equipment being dismantled. The thicker the metal being cut, the higher the attrition rate for things such as cutting blades. The range of consumables costs at BR3 have been in the range of MSEK 0.1 to 0.2/m{sup 2} dismantled. The extent of detailed information available in the 1996 Aagesta estimate is not sufficient to enable a full comparison with the BR3 decommissioning results. A global first comparison has been attempted by summing the resources expended on the BR3 work packages described in this report with the combined dismantling data presented in the 1996 Aagesta cost estimate report. Very broadly the cost of decontamination plus dismantling of the main process equipment at Aagesta appears to be in the order of MSEK 70, of which MSEK 4 is labour on preparatory/planning work, MSEK 40 is labour on actual decontamination and dismantling and MSEK

  12. Decommissioning of the Molten Salt Reactor Experiment: A technical evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Notz, K.J.

    1988-01-01

    This report completes a technical evaluation of decommissioning planning for the former Molten Salt Reactor Experiment, which was shut down in December, 1969. The key issues revolve around the treatment and disposal of some five tons of solid fuel salt which contains over 30 kg of fissionable uranium-233 plus fission products and higher actinides. The chemistry of this material is complicated by the formation of elemental fluorine via a radiolysis reaction under certain conditions. Supporting studies carried out as part of this evaluation include (a) a broad scope analysis of possible options for storage/disposal of the salts, (b) calculation of nuclide decay in future years, (c) technical evaluation of the containment facility and hot cell penetrations, (d) review and update of surveillance and maintenance procedures, (e) measurements of facility groundwater radioactivity and sump pump operation, (f) laboratory studies of the radiolysis reaction, and (g) laboratory studies which resulted in finding a suitable getter for elemental fluorine. In addition, geologic and hydrologic factors of the surrounding area were considered, and also the implications of entombment of the fuel in-place with concrete. The results of this evaluation show that the fuel salt cannot be left in its present form and location permanently. On the other hand, extended storage in its present form is quite acceptable for 20 to 30 years, or even longer. For continued storage in-place, some facility modifications are recommended. 30 refs., 5 figs., 9 tabs.

  13. Decommissioning of the High Flux Beam Reactor at Brookhaven Lab

    Energy Technology Data Exchange (ETDEWEB)

    Hu, J. P. [Brookhaven National Lab. (BNL), Upton, NY (United States); Reciniello, R. N. [Brookhaven National Lab. (BNL), Upton, NY (United States); Holden, N. E. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2011-05-27

    The High Flux Beam Reactor at the Brookhaven National Laboratory was a heavy water cooled and moderated reactor that achieved criticality on October 31, 1965. It operated at a power level of 40 mega-watts. An equipment upgrade in 1982 allowed operations at 60 mega-watts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 mega-watts. The HFBR was shutdown in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of ground water from wells located adjacent to the reactor’s spent fuel pool. The reactor remained shutdown for almost three years for safety and environmental reviews. In November 1999 the United States Department of Energy decided to permanently shutdown the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome which still contains the irradiated reactor vessel is presently under 24/7 surveillance for safety. Details of the HFBR cleanup conducted during 1999-2009 will be described in the paper.

  14. Fission-Product Development Laboratory cell-decommissioning project plan

    Energy Technology Data Exchange (ETDEWEB)

    Myrick, T.E.; Schaich, R.W.; Williams, F.V.

    1983-08-01

    The Fission Product Development Laboratory (FPDL) at Oak Ridge National Laboratory (ORNL) was a full-scale processing facility for separating megacurie quantities of /sup 90/Sr, /sup 137/Cs, and /sup 144/Ce for a variety of source applications, operating at full capacity from 1958 to 1975. Since facility shutdown, the inactive portions of the FPDL have been maintained in a protective storage mode as part of the ORNL Surplus Facilities Management Program (SFMP). Due to the significant radio-nuclide inventory remaining in the facility, the high surveillance and maintenance costs necessary to assure radionuclide containment, and the potential for reuse of the facility by other programs, the decommissioning of the inactive portions of the FPDL has been given a high priority by the SFMP. In response to this program direction, plans are being made for initiation of these activities in late FY 1983. This project plan has been prepared to satisfy the program documentation requirements for SFMP project planning. The plan outlines the scope of the proposed effort, describes the proposed methods of project accomplishment, and provides estimates of the project resource needs and schedule.

  15. Desempenho em confinamento de machos bovinos inteiros Canchim, Aberdeen angus e cruzamentos recíprocos

    Directory of Open Access Journals (Sweden)

    Perotto Daniel

    2002-01-01

    Full Text Available Foram analisados o consumo diário de matéria seca (MS por 100kg de peso vivo (CMS, a conversão alimentar (CA e o ganho de peso médio diário (GMD de 118 machos bovinos inteiros Canchim (Cn, Aberdeen Angus (Ab e cruzamentos recíprocos (CnAb (F1, 3/4Cn+1/4Ab, 5/8Cn+3/8Ab e 11/16Cn+5/16Ab e AbCn (F1, 5/8Ab+3/8Cn e 11/16Ab+5/16Cn. Esses animais foram alimentados em baias individuais por 84 a 95 dias com silagem de milho à vontade mais concentrado (17,8% de PB e 79% de NDT fornecido à base de 1% do peso vivo do animal por dia. As características foram analisadas por um modelo que incluiu os efeitos fixos de ano do confinamento, grupo genético, período e ano x período e o efeito aleatório de animal dentro de grupo genético dentro de ano. A relação MS do concentrado:MS da silagem foi incluída como co-variável no modelo. Posteriormente, as características foram analisadas por um modelo de regressão que incluiu coeficientes representando as frações esperadas de Ab nos genótipos dos animais e das mães e as heterozigoses individual e materna. As médias para CMS, CA e GMD foram 2,44kg de MS/100kg de PV/dia, 6,97kg de MS/kg de GMD e 1,435kg/dia, respectivamente. O grupo genético influenciou o CMS (P<0,01 e o GMD (P<0,06. O Ab igualou-se ao AbCn apresentando maior CMS e menor GMD que o Cn e o CnAb. Não houve heterose para qualquer das características indicando que o cruzamento alternado Cn x Ab seria igual à média das raças paternas.

  16. Analysis of the Possibility of Required Resources Estimation for Nuclear Power Plant Decommissioning Applying BIM

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu [Korea Institute of construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Estimation of decommissioning cost, decommissioning strategy, and decommissioning quantity at the time when entering into any decommissioning plans are some elements whose inputs are mandatory for nuclear power plant decommissioning. Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. This study aims at analyzing whether required resources for decommissioning nuclear power plants can be estimated, applying BIM. To achieve this goal, this study analyzed the status quo of BIM such as definition, characteristics, and areas applied, and made use of them when drawing out study results by examining types and features of the tools realizing BIM. In order to review how BIM could be used for decommissioning nuclear power plants, the definition, characteristics and applied areas of BIM were discussed. BIM designs objects of the structures (walls, slabs, pillars, stairs, windows and doors, etc.) by 3D technology and endows attribute (function, structure and usage) information for each object, thereby providing visualized information of structures for participants in construction projects. Major characteristics of BIM attribute information are as follows: - Geometry: The information of objects is represented by measurable geometric information - Extensible object attributes: Objects include pre-defined attributes, and allow extension of other attributes. Any model that includes these attributes forms relationships with other various attributes in order to perform analysis and simulation. - All information including the attributes are integrated to ensure continuity, accuracy and accessibility, and all information used during the life cycle of structures are supported. This means that when information of required resources is added as another attributes other than geometric

  17. Ringhals Site Study 2013 - An assessment of the decommissioning cost for the Ringhals site

    Energy Technology Data Exchange (ETDEWEB)

    Hansson, Tommy [Ringhals AB, Ringhals (Sweden); Norberg, Thomas [Solvina AB, Goeteborg (Sweden); Knutsson, Andreas; Fors, Patrik; Sandebert, Camilla [Vattenfall AB, Stockholm (Sweden)

    2013-03-15

    This report presents the decommissioning cost for the Ringhals site as of 2013. The objective has been to make a best estimate of the costs within the uncertainties of a budgetary estimate. To achieve this, the decommissioning costs have been assessed with support from TLG Services Inc., utilizing their knowledge and experience from U.S. decommissioning projects incorporated in their cost estimation platform DECCER. The 2013 estimate has included the development of a Ringhals-specific cost estimation method that allows for successive improvement in the future. In-house experiences have been included and the method is based on the present decommissioning strategy according to Ringhals decommissioning plan. Two basic approaches have been used in the cost assessment; a bottom up approach to develop unit cost factors (UCF) for recurrent work; and a specific analogy approach for cost estimating special items. The basic, activity-dependent, costs have been complemented by period-dependent costs, derived, among other things, from SKB's newly developed reference planning and organizational model for a Swedish decommissioning project. Furthermore, collateral costs based on the experiences of Barsebaeck have been included. As a final point, all costs have been adjusted for industrial standard contingencies, as suggested by TLG, to achieve a best estimate. In order to make the cost intelligible a comprehensive description of the assumptions, boundary conditions and general basis of the estimate is included in this report. All costs have been reported both according to the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations published by OECD/NEA and according to the SKB developed EEF structure. Furthermore, common costs have been isolated to a theoretical unit 0 to make the cost for respective unit even more comparable on a national and international scale. The calculations show that the total cost for the decommissioning of the Ringhals

  18. Decommissioning of a mixed oxide fuel fabrication plant at Winfrith Technolgy Centre

    Energy Technology Data Exchange (ETDEWEB)

    Pengelly, M.G.A. [AEA Technology, Dorchester (United Kingdom)

    1994-01-01

    The Alpha Materials Laboratory (Building A52) at Winfrith contained a mixed oxide fuel fabrication plant which had a capability of producing 10 te/yr of pelleted/compacted fuel and was in operation from 1962 until 1980, when the requirement for this type of fuel in the UK diminished, and the plant became surplus to requirements. A program to develop decommissioning techniques for plutonium plants was started in 1983, addressing the following aspects of alpha plant decommissioning: (1) Re-usable containment systems, (2) Strippable coating technology, (3) Mobile air filtration plant, (4) Size reduction primarily using cold cutting, (5) techniques, (6) Waste packing, and (7) Alpha plant decommissioning methodology. The technology developed has been used to safely and efficiently decommission radioactive plant and equipment including Pu contaminated glove boxes. (63 glove boxes to date) The technology has been widely adopted in the United Kingdom and elsewhere. This paper outlines the general strategies adopted and techniques used for glove box decommissioning in building A52.

  19. Decommissioning of the nuclear facilities at Risø National Laboratory. Descriptions and cost assessment

    DEFF Research Database (Denmark)

    Lauridsen, K.

    2001-01-01

    The report is the result of a project initiated by Risø National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risø National Laboratory to be decommissioned and gives anassessment of the work to be done and the ......The report is the result of a project initiated by Risø National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risø National Laboratory to be decommissioned and gives anassessment of the work to be done...... and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing forthe longer decay periods; some operations still will need to be performed remotely....... Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to betransferred to a Danish repository. For a revision of the cost estimate for the decommissioning of the research Reactor DR 3 please consult...

  20. Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

    Energy Technology Data Exchange (ETDEWEB)

    Denahm, D. H.; Barnes, M. G.; Jaquish, R. E.; Corley, J. P.; Gilbert, R. O.; Hoenes, G. R.; Jamison, J. D.; McMurray, B. J.; Watson, E. C.

    1983-08-01

    This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations.

  1. Fugitive emissions of methane from abandoned, decommissioned oil and gas wells

    Science.gov (United States)

    Worrall, Fred; boothroyd, Ian; Almond, Sam; Davies, Richard

    2015-04-01

    The aim of this study was to consider the potential legacy of increased onshore, unconventional gas production by examining the integrity of decommissioned, onshore, oil and gas wells in the UK. In the absence of a history of unconventional hydrocarbon exploitation in the UK, conventional onshore sites were considered and an examination of pollution incidents records had suggested that only a small fraction of onshore wells could show integrity failures. In this study the fugitive emissions of methane from former oil and gas production wells onshore in the UK were considered as a measure of well integrity. The survey considered 49 decommissioned (abandoned) wells from 4 different basins that were between 8 and 78 years old; all but one of these wells would be considered as having been decommissioned properly, i.e. wells cut, sealed and buried by soil cover to the extent that the well sites were being used for agriculture. For each well site the soil gas methane was analysed multiple times and assessed relative to a nearby control site of similar land-use and soil type. The results will be expressed in terms of the proportion and extent of well integrity failure, or success, over time since decommissioning and relative to local control sites. The probability of failure and the emissions factor for decommissioned wells will be presented.

  2. Conceptual and numerical models of the glacial aquifer system north of Aberdeen, South Dakota

    Science.gov (United States)

    Marini, Katrina A.; Hoogestraat, Galen K.; Aurand, Katherine R.; Putnam, Larry D.

    2012-01-01

    This U.S. Geological Survey report documents a conceptual and numerical model of the glacial aquifer system north of Aberdeen, South Dakota, that can be used to evaluate and manage the city of Aberdeen's water resources. The glacial aquifer system in the model area includes the Elm, Middle James, and Deep James aquifers, with intervening confining units composed of glacial till. The Elm aquifer ranged in thickness from less than 1 to about 95 feet (ft), with an average thickness of about 24 ft; the Middle James aquifer ranged in thickness from less than 1 to 91 ft, with an average thickness of 13 ft; and the Deep James aquifer ranged in thickness from less than 1 to 165 ft, with an average thickness of 23 ft. The confining units between the aquifers consisted of glacial till and ranged in thickness from 0 to 280 ft. The general direction of groundwater flow in the Elm aquifer in the model area was from northwest to southeast following the topography. Groundwater flow in the Middle James aquifer was to the southeast. Sparse data indicated a fairly flat potentiometric surface for the Deep James aquifer. Horizontal hydraulic conductivity for the Elm aquifer determined from aquifer tests ranged from 97 to 418 feet per day (ft/d), and a confined storage coefficient was determined to be 2.4x10-5. Estimates of the vertical hydraulic conductivity of the sediments separating the Elm River from the Elm aquifer, determined from the analysis of temperature gradients, ranged from 0.14 to 2.48 ft/d. Average annual precipitation in the model area was 19.6 inches per year (in/yr), and agriculture was the primary land use. Recharge to the Elm aquifer was by infiltration of precipitation through overlying outwash, lake sediments, and glacial till. The annual recharge for the model area, calculated by using a soil-water-balance method for water year (WY) 1975-2009, ranged from 0.028 inch in WY 1980 to 4.52 inches in WY 1986, with a mean of 1.56 inches. The annual potential

  3. The development of the strategy and plan for the decommissioning and abandonment of 36'' offshore oil export pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Richard J. [PIMS of London Ltd, London, (United Kingdom); Galvez Reyes, Marco Antonio [PEMEX Refinacion, Veracruz, (Mexico)

    2010-07-01

    The decommissioning and abandonment of platforms and pipelines are big challenges for the pipeline industry. This paper presents a review of the decommissioning and abandonment processes based on a study case, the Rabon Grande pipeline system. First, the applicable international codes, standards and regulations associated with the decommissioning of pipelines are discussed. Next, this paper presents a review of the decommissioning and abandonment options and considerations available for the study case. The Rabon Grande pipeline system, which was shut down and isolated in 1990 pending decommissioning, is used as an example of applying decommissioning and abandonment best practice and establishing a realistic scope of work. A decommissioning plan is developed in light of these previous studies, followed by an environmental impact assessment. It is found that contrary to what was done in the case of the Rabon Grande pipeline, when a pipeline is to be shutdown, the best practice methodology is to temporally or fully decommission the system as soon as possible.

  4. Características da carcaça de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos terminados em confinamento Carcass traits of Canchim, Aberdeen Angus and reciprocal crosses finished in confinement

    OpenAIRE

    Daniel Perotto; José Luiz Moletta; Antonio Carlos Cubas

    1999-01-01

    Foram analisadas quatorze características quantitativas das carcaças de 137 machos bovinos inteiros pertencentes aos grupos Canchim (Ca), Aberdeen Angus (Ab), 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab e 5/8Ab+3/8Ca, nascidos na Estação Experimental Fazenda Modelo, em Ponta Grossa-PR, no período de 1988 a 1993. As médias para a idade e para o peso ao início do confinamento, duração do confinamento, idade e peso ao abate foram, respectivamente, 737 dias, 356kg, 97 dias, 834 dias e 468kg. Durante o ...

  5. Tradução e adaptação cultural do Questionário Aberdeen para Veias Varicosas Translation and cultural adaptation of Aberdeen Varicose Veins Questionnaire

    Directory of Open Access Journals (Sweden)

    Flávia de Jesus Leal

    2012-03-01

    Full Text Available CONTEXTO: Atualmente há um crescente interesse por instrumentos de avaliação em saúde produzidos e validados em todo o mundo. Apesar disso, ainda não temos no Brasil instrumentos que avaliem o impacto da doença venosa crônica na vida de seu portador. Para utilização dessas medidas torna-se necessária a realização da tradução e da adaptação cultural ao idioma em questão. OBJETIVO: Traduzir e adaptar culturalmente para a população brasileira o Aberdeen Varicose Veins Questionnaire (AVVQ- Brasil. MÉTODOS: O processo consistiu de duas traduções e duas retrotraduções realizadas por tradutores independentes, da avaliação das versões seguida da elaboração de versão consensual e de pré-teste comentado. RESULTADOS: Os pacientes do pré-teste eram do sexo feminino, com média de idade de 49,9 anos, média de tempo de resposta 7,73 minutos, que variou entre 4,55 minutos (tempo mínimo a 10,13 minutos (tempo máximo. Escolaridade: 20% analfabetismo funcional, 1º grau completo e 2º grau completo; 30% 1º grau incompleto; e 10% 3º grau completo. Gravidade clínica 40% C3 e C6S, 10% C2 e C5, havendo cinco termos incompreendidos na aplicação. CONCLUSÕES: A versão na língua portuguesa do Aberdeen Varicose Veins Questionnaire está traduzida e adaptada para uso na população brasileira, podendo ser utilizada após posterior análise de suas propriedades clinimétricas.BACKGROUND: Currently there is a growing interest in health assessment tools produced and validated throughout the world. Nevertheless, it is still inadequate the number of instruments that assess the impact of chronic venous disease in the life of its bearer. To use these measures it is necessary to accomplish the translation and cultural adaptation to the language in question. OBJECTIVE: Translate to Portuguese and culturally adapted for the Brazilian population the Aberdeen Varicose Veins Questionnaire (AVVQ-Brazil. METHODS: The process consisted of two

  6. Decontamination and decommissioning activities photobriefing book FY 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-08

    The Chicago Pile 5 (CP-5) Reactor, the first reactor built on the Argonne National Laboratory-East site, followed a rich history that had begun in 1942 with Enrico Fermi's original pile built under the west stands at the Stagg Field Stadium of The University of Chicago. CP-5 was a 5-megawatt, heavy water-moderated, enriched uranium-fueled reactor used to produce neutrons for scientific research from 1954--79. The reactor was shut down and defueled in 1979, and placed into a lay-up condition pending funding for decontamination and decommissioning (D and D). In 1990, work was initiated on the D and D of the facility in order to alleviate safety and environmental concerns associated with the site due to the deterioration of the building and its associated support systems. A decision was made in early Fiscal Year (FY) 1999 to direct focus and resources to the completion of the CP-5 Reactor D and D Project. An award of contract was made in December 1998 to Duke Engineering and Services (Marlborough, MA), and a D and D crew was on site in March 1999 to begin work, The project is scheduled to be completed in July 2000. The Laboratory has determined that the building housing the CP-5 facility is surplus to the Laboratory's needs and will be a candidate for demolition. In addition to a photographic chronology of FY 1999 activities at the CP-5 Reactor D and D Project, brief descriptions of other FY 1999 activities and of projects planned for the future are provided in this photobriefing book.

  7. DEVELOPMENT OF PERSONAL PROTECTIVE EQUIPMENT FOR DECONTAMINATION AND DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Ebadian, Ph.D.

    1999-01-01

    The purpose of this one-year investigation is to perform a technology integration/search, thereby ensuring that the safest and most cost-effective options are developed and subsequently used during the deactivation and decommissioning (D&D) of U.S. Department of Energy Environmental Management (DOE-EM) sites. Issues of worker health and safety are the main concern, followed by cost. Two lines of action were explored: innovative Personal Cooling Systems (PCS) and Personal Monitoring Equipment (PME). PME refers to sensors affixed to the worker that warn of an approaching heat stress condition, thereby preventing it. Three types of cooling systems were investigated: Pre-Chilled or Forced-Air System (PCFA), Umbilical Fluid-Chilled System (UFCS), and Passive Vest System (PVS). Of these, the UFCS leads the way. The PVS or Gel pack vest lagged due to a limited cooling duration. And the PCFA or chilled liquid air supply was cumbersome and required an expensive and complex recharge system. The UFCS in the form of the Personal Ice Cooling System (PICS) performed exceptionally. The technology uses a chilled liquid circulating undergarment and a Personal Protective Equipment (PPE) external pump and ice reservoir. The system is moderately expensive, but the recharge is low-tech and inexpensive enough to offset the cost. There are commercially available PME that can be augmented to meet the DOE's heat stress alleviation need. The technology is costly, in excess of $4,000 per unit. Workers easily ignore the alarm. The benefit to health & safety is indirect so can be overlooked. A PCS is a more justifiable expenditure.

  8. DEACTIVATION AND DECOMMISSIONING (D AND D) TECHNOLOGY INTEGRATION

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Ebadian, Ph.D.

    1999-01-01

    As part of the ongoing task of making Deactivation and Decommissioning (D&D) operations more efficient, this subtask has addressed the need to integrate existing characterization technologies with decontamination technologies in order to provide real-time data on the progress of contamination removal. Specifically, technologies associated with concrete decontamination and/or removal have been examined with the goal of integrating existing technologies and commercializing the resulting hybrid. The Department of Energy (DOE) has estimated that 23 million cubic meters of concrete will require disposition as 1200 buildings undergo the D&D process. All concrete removal to be performed will also necessitate extensive use of characterization techniques. The in-process characterization presents the most potential for improvement and cost-savings as compared to other types. Current methods for in-process characterization usually require cessation of work to allow for radiation surveys to assess the rate of decontamination. Combining together decontamination and characterization technologies would allow for in-process evaluation of decontamination efforts. Since the present methods do not use in-process evaluations for the progress of decontamination, they may allow for ''overremoval'' of materials (removal of contaminated along with non-contaminated materials). Overremoval increases the volume of waste and therefore the costs associated with disposal. Integrating technologies would facilitate the removal of only contaminated concrete and reduce the total volume of radioactive waste, which would be disposed of. This would eventually ensure better productivity and time savings. This project presents a general procedure to integrate the above-mentioned technologies in the form of the Technology Integration Module (TIM) along with combination lists of commercially available decontamination and characterization technologies. The scope of the project has also

  9. Mobile worksystems for decontamination and decommissioning operations. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

  10. Comparative analysis of the Oskarshamn 3 and Barsebaeck site decommissioning studies

    Energy Technology Data Exchange (ETDEWEB)

    Hansson, Bertil (Bewon, Loeddekoepinge (Sweden)); Joensson, Lars-Olof (Barsebaeck Kraft AB, Loeddekoepinge (Sweden))

    2009-01-15

    Several projects concerning the decommissioning of different types of nuclear facilities have shown that technical methods and equipment are available today for safe dismantling of nuclear facilities of any type or size. However, comparison of individual cost estimates for specific facilities exhibit relatively large variations, and several studies have tried to identify the reasons for these variations. Analysis has shown that decommissioning cost estimates vary depending on a number of factors, including: the boundary conditions and strategy chosen; the cost items taken into account; the origin of the cost estimate; the methodology applied; the political-administrative framework; and the way contingencies are included. In this study, a comparison has been made between two decommissioning studies in the same country, with more or less same decommissioning schedule and with similar overall ideas on cost estimates. However, the two studies had from the start a different focus and different objectives. One study is intended as a reference study for all BWRs in Sweden, while the other focuses on a full site decommissioning. Furthermore, one of the studies is based on direct dismantling and the other on deferred dismantling. A great deal of work therefore had to be devoted in the present study to giving the studies comparable structures and boundary conditions using the OECD/NEA cost estimate structure. The boundary conditions in each of the studies have been thoroughly evaluated qualitatively and quantitatively, and the differences have been explained. In the end, values have been set in the quantitative analysis to verify that the studies could be compared, within the accuracy of what is defined in the industry as a 'budgetary estimate'. Differences still exist relating to what has been included in the studies and to the decommissioning plans and the resulting inventory from site characterization. Such differences must be accepted as long as it is clear

  11. Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Elder, H. K.

    1981-10-01

    Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0

  12. 30 CFR 285.517 - How will MMS determine the amounts of the supplemental and decommissioning financial assurance...

    Science.gov (United States)

    2010-07-01

    ... supplemental and decommissioning financial assurance requirements associated with commercial leases? 285.517... Assurance Requirements Financial Assurance Requirements for Commercial Leases § 285.517 How will MMS... decommissioning financial assurance requirements on estimates of the cost to meet all accrued lease...

  13. Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 1. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, C. E.; Murphy, E. S.; Schneider, K J

    1979-01-01

    Detailed technology, safety and cost information are presented for the conceptual decommissioning of a reference small mixed oxide fuel fabrication plant. Alternate methods of decommissioning are described including immediate dismantlement, safe storage for a period of time followed by dismantlement and entombment. Safety analyses, both occupational and public, and cost evaluations were conducted for each mode.

  14. 30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Science.gov (United States)

    2010-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 285.902 Section 285.902 Mineral Resources... SAP, COP, or GAP? (a) Except as otherwise authorized by MMS under § 285.909, within 2 years following... under your SAP, COP, or GAP, you must submit a decommissioning application and receive approval from...

  15. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment[Denmark

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt [ed.

    2001-02-01

    The report is the result of a project initiated by Risoe National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risoe National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing for the longer decay periods; some operations still will need to be performed remotely. Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to be transferred to a Danish repository. (au)

  16. Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

  17. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  18. Survey of technology for decommissioning of nuclear fuel cycle facilities. 8. Remote handling and cutting techniques

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-03-01

    In nuclear fuel cycle facility decommissioning and refurbishment, the remote handling techniques such as dismantling, waste handling and decontamination are needed to reduce personnel radiation exposure. The survey research for the status of R and D activities on remote handling tools suitable for nuclear facilities in the world and domestic existing commercial cutting tools applicable to decommissioning of the facilities was conducted. In addition, the drive mechanism, sensing element and control system applicable to the remote handling devices were also surveyed. This report presents brief surveyed summaries. (H. Itami)

  19. AMNT 2014. Key Topic: Fuel, decommissioning and disposal - report. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Seipolt, Thomas [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany); Weber, Stefan [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany); Kock, Ingo [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) GmbH, Koeln (Germany)

    2015-02-15

    Summary report on the following Topical Sessions of the Key Topic 'Fuel, Decommissioning and Disposal' of the Annual Conference on Nuclear Technology held in Frankfurt, 6 to 8 May 2014: - From Pilot Project to an Industrial Service (Thomas Seipolt); - Radioactive Waste Management - Experiences with Interim and Final Storage (Stefan Weber and Ingo Kock). The other Sessions of the Key Topics 'Reactor Operation, Safety', 'Competence, Innovation, Regulation' and 'Fuel, Decommissioning and Disposal' have been covered in atw 10 and 12 (2014), 1 (2015) and will be covered in further issues of atw.

  20. Determination of the activation level in the decommissioning inventory of the NPP Krsko

    Energy Technology Data Exchange (ETDEWEB)

    Jaag, S.; Graebner, G.; Keck, B. [NIS Ingenieurgesellschaft mbH, Alzenau (Germany); Glaser, B. [Nuklearna Elektrarna Krsko (Slovenia)

    2010-05-15

    In support of a plant specific preliminary decommissioning plan the MCNP 5 code system /1/ was used to model the Krsko-reactor core and its external components relevant for activation analysis and decommissioning in 3D-geometry. By MCNP neutron transport calculations transfer functions for the space-dependent total neutron flux and the space-dependent rates (1-group cross sections) of the most relevant nuclear reactions were generated. These transfer functions were combined with the reactor operational data, and ORIGEN-2.1 /2/ irradiation calculations were performed to provide the activation levels of the individual reactor components. The results are presented and the uncertainties are discussed. (orig.)

  1. Fiscal years 1993 and 1994 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Decontamination and Decommissioning Projects Department

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This photobriefing book describes the ongoing decontamination and decommissioning projects at the Argonne National Laboratory (ANL)-East Site near Lemont, Illinois. The book is broken down into three sections: introduction, project descriptions, and summary. The introduction elates the history and mission of the Decontamination and Decommissioning (D and D) Projects Department at ANL-East. The second section describes the active ANL-East D and D projects, giving a project history and detailing fiscal year (FY) 1993 and FY 1994 accomplishments and FY 1995 goals. The final section summarizes the goals of the D and D Projects Department and the current program status. The D/D projects include the Experimental Boiling Water Reactor, Chicago Pile-5 Reactor, that cells, and plutonium gloveboxes. 73 figs.

  2. Decommissioning in the oil and gas industry and the inclusion of decommissioning permit in the Brazilian system of environmental permitting - first thoughts; O descomissionamento na industria de petroleo e gas e a inclusao da licenca de desinstalacao no procedimento de licenciamento ambiental brasileiro - primeiras reflexoes

    Energy Technology Data Exchange (ETDEWEB)

    Bezerra, Luiz Gustavo Escorcio [Stroeter e Royster Advogados, Sao Paulo, SP (Brazil)]|[Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil). Faculdade de Direito. Programa de Estudos e Pesquisa em Direito do Petroleo (ANP - PRH33)

    2005-07-01

    This paper aims to promote discussions regarding the decommissioning issue, its role in the protection of the environment and the feasibility of the inclusion of a Decommissioning Permit in the Brazilian System of Environmental Permitting. (author)

  3. 75 FR 8147 - Notice of Consideration of Amendment Request for Decommissioning of Analytical Bio-Chemistry...

    Science.gov (United States)

    2010-02-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Notice of Consideration of Amendment Request for Decommissioning of Analytical Bio-Chemistry...-Chemistry Laboratories, Inc. (the Licensee) pursuant to 10 CFR part 30. By application dated October...

  4. Nuclear power plant decommissioning. (Latest citations from the NTIS bibliographic database). Published Search

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    The bibliography contains citations concerning phase-out and decommissioning of nuclear power plants worldwide. Included are case histories of the dismantling process, hazardous waste management, site monitoring, and economic aspects of the phase-out. Examples include European, Chinese, Eastern European, and United States facilities. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  5. Nuclear power plant decommissioning. (Latest citations from the NTIS bibliographic database). Published Search

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The bibliography contains citations concerning phase-out and decommissioning of nuclear power plants worldwide. Included are case histories of the dismantling process, hazardous waste management, site monitoring, and economic aspects of the phase-out. Examples include European, Chinese, Eastern European, and United States facilities. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  6. 75 FR 13568 - MMS Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Science.gov (United States)

    2010-03-22

    ..., Decommissioning Activities. OMB Control Number: 1010-0142. Abstract: The Outer Continental Shelf (OCS) Lands Act... prevent or minimize the likelihood of blowouts, loss of well control, fires, spillages, physical... cleared of obstructions; remove casing stub or mud line suspension equipment and subsea...

  7. 78 FR 38739 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Science.gov (United States)

    2013-06-27

    ..., DG-1272, in the Federal Register on December 19, 2012 (77 FR 75198), for a 60-day public comment... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... (NRC) is issuing Revision 1 of Regulatory Guide (RG) 1.185, ``Standard Format and Content for...

  8. Allowable Residual Contamination Levels in soil for decommissioning the Shippingport Atomic Power Station site

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

    1983-09-01

    As part of decommissioning the Shippingport Atomic Power Station, a fundamental concern is the determination of Allowable Residual Contamination Levels (ARCL) for radionuclides in the soil at the site. The ARCL method described in this report is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for unrestricted use of the land after decommissioning. In addition to naturally occurring radionuclides and fallout from weapons testing, soil contamination could potentially come from five other sources. These include operation of the Shippingport Station as a pressurized water reactor, operations of the Shippingport Station as a light-water breeder, operation of the nearby Beaver Valley reactors, releases during decommissioning, and operation of other nearby industries, including the Bruce-Mansfield coal-fired power plants. ARCL values are presented for 29 individual radionculides and a worksheet is provided so that ARCL values can be determined for any mixture of the individual radionuclides for any annual dose limit selected. In addition, a worksheet is provided for calculating present time soil concentration value that will decay to the ARCL values after any selected period of time, such as would occur during a period of restricted access. The ARCL results are presented for both unconfined (surface) and confined (subsurface) soil contamination. The ARCL method and results described in this report provide a flexible means of determining unrestricted-use site release conditions after decommissioning the Shippingport Atomic Power Station.

  9. Evaluation of Dam Decommissioning in an Ice-Affected River: Case Study

    Science.gov (United States)

    2007-09-01

    Abdul-Mohsen 2005 and Kuby et al. 2005). Conyngham et al. (2006) provide an overview of the ecological and engi- neering aspects of dam decommissioning...2007) CRREL Ice Jam Database (http://www.crrel.usace.army.mil/ierd/ijdb/), accessed March 2007. Kuby , M.J., W.F. Fagan, C.S. ReVelle, W.L. Graf (2005

  10. Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396

    Energy Technology Data Exchange (ETDEWEB)

    Devgun, Jas S. [Nuclear Power Technologies, Sargent and Lundy LLC, Chicago, IL (United States); Laraia, Michele [private consultant, formerly from IAEA, Kolonitzgasse 10/2, 1030, Vienna (Austria); Pescatore, Claudio [OECD, Nuclear Energy Agency, Issy-les-Moulineaux, Paris (France); Dinner, Paul [International Atomic Energy Agency, Wagramerstrasse 5, A-1400 Vienna (Austria)

    2012-07-01

    Accidents at the Fukushima Dai-ichi reactors as a result of the devastating earthquake and tsunami of March 11, 2011 have not only dampened the nuclear renaissance but have also initiated a re-examination of the design and safety features for the existing and planned nuclear reactors. Even though failures of some of the key site features at Fukushima can be attributed to events that in the past would have been considered as beyond the design basis, the industry as well as the regulatory authorities are analyzing what features, especially passive features, should be designed into the new reactor designs to minimize the potential for catastrophic failures. It is also recognized that since the design of the Fukushima BWR reactors which were commissioned in 1971, many advanced safety features are now a part of the newer reactor designs. As the recovery efforts at the Fukushima site are still underway, decisions with respect to the dismantlement and decommissioning of the damaged reactors and structures have not yet been finalized. As it was with Three Mile Island, it could take several decades for dismantlement, decommissioning and clean up, and the project poses especially tough challenges. Near-term assessments have been issued by several organizations, including the IAEA, the USNRC and others. Results of such investigations will lead to additional improvements in system and site design measures including strengthening of the anti-tsunami defenses, more defense-in-depth features in reactor design, and better response planning and preparation involving reactor sites. The question also arises what would the effect be on the decommissioning scene worldwide, and what would the effect be on the new reactors when they are eventually retired and dismantled. This paper provides an overview of the US and international activities related to recovery and decommissioning including the decommissioning features in the reactor design process and examines these from a new

  11. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FORTHE DECOMMISSIONING OF THE FUEL CHANNELS IN THECANDU NUCLEAR REACTOR

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2013-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of theseinstallations has become one of the 21stcentury’s great challenges. Each project may be managed differently,depending on the country, development policies, financial considerations, and the availability of qualifiedengineers or specialized companies to handle such projects. The principle objective of decommissioning is toplace a facility into such a condition that there is no unacceptable risk from the decommissioned facility topublic health and safety of the environment. In order to ensure that at the end of its life the risk from a facility iswithin acceptable bounds, action is normally required. The overall decommissioning strategy is todeliver a timely, cost-effective program while maintaining high standards of safety, security and environmentalprotection. If facilities were not decommissioned, they could degrade and potentially present an environmentalradiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is notconsidered to be an acceptable alternative to decommissioning. The final aim of decommissioning is torecover the geographic site to its original condition.

  12. Proceedings of the Workshop on Acute Lung Injury and Pulmonary Edema Held in Aberdeen Proving Ground, Maryland on 4-5 May 1989

    Science.gov (United States)

    1989-11-01

    with side effects, including pulmonary edema . The objective of this study was to determine if the pulmonary edema was cardiogenic or noncardio- genic...Proeedings ~FL gof the .1Workshop on Acute Lung Injury and Pulmonary Edema 4-5 May 1989a Aberdeen Proving Ground, Maryland I7 21 Sponsored by the...TITLE (include Security Classification) (U) Proceedings of the" Workshop on Acute Lung Injury and Pulmonary Edema , May 1989 12. PERSONAL AUTHOR(S) David

  13. Sixteen Years of International Co-operation. The OECD/NEA Co-operative Programme on Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Menon, S.; Valencia, L.

    2002-02-25

    The Co-operative Programme on Decommissioning under the administration of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA) has recently completed sixteen years of operation. The Programme, which is essentially an information exchange programme between decommissioning projects, came into being in 1985. It has grown from an initial 10 decommissioning projects from 7 countries to 39 projects from 14 countries today. From purely information exchange to start with, the Programme has, in later years, been functioning as a voice for the collective expression of views of the implementers of nuclear decommissioning. During the first sixteen years of the operation of the Co-operative Programme, nuclear decommissioning has grown from local specialist activities within projects to a competitive commercial industry. By the dismantling and release from regulatory control of over a dozen diverse nuclear facilities, the Programme has been able to demonstrate in practice, that nuclear decommissioning can be performed safely both for the workers and the public, and that this can be done at reasonable costs in an environmentally friendly fashion. During the recent years, discussions and work within the Co-operative Programme, specially within some of the Task Groups, have had/are having effects and repercussions not just in the field of nuclear decommissioning, but can possibly affect activities and regulations in other industries. This paper describes how the Programme and its activities and procedures have evolved over the years and indicate the directions of developments in the organization and execution of decommissioning projects. Finally, it gives a brief overview of the achievements of the Cooperative Programme and visualizes future developments in the field of nuclear decommissioning.

  14. Hot Chemistry Laboratory decommissioning activities at IPEN/CNEN-SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Camilo, Ruth L.; Lainetti, Paulo E.O. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: rcamilo@ipen.br, e-mail: lainetti@ipen.br

    2009-07-01

    IPEN's fuel cycle activities were accomplished in laboratory and pilot plant scale and most facilities were built in the 70-80 years. Nevertheless, radical changes of the Brazilian nuclear policy in the beginning of 90's determined the interruption of several fuel cycle activities and facilities shutdown. Since then, IPEN has faced the problem of the pilot plants decommissioning considering that there was no experience/expertise in this field at all. In spite of this, some laboratory and pilot plant decommissioning activities have been performed in IPEN in the last years, even without previous experience and training support. One of the first decommissioning activities accomplished in IPEN involved the Hot Chemistry Laboratory. This facility was built in the beginning of the 80's with the proposal of supporting research and development in the nuclear chemistry area. It was decided to settle a new laboratory in the place where the Hot Chemistry Laboratory was installed, being necessary its total releasing from the radioactive contamination point of view. The previous work in the laboratory involved the manipulation of samples of irradiated nuclear fuel, besides plutonium-239 and uranium-233 standard solutions. There were 5 glove-boxes in the facility but only 3 were used with radioactive material. The glove-boxes contained several devices and materials, besides the radioactive compounds, such as: electric and electronic equipment, metallic and plastic pieces, chemical reagents, liquid and solid radioactive wastes, etc. The laboratory's decommissioning process was divided in 12 steps. This paper describes the procedures, problems faced and results related to the Hot Chemistry Laboratory decommissioning operations and its reintegration as a new laboratory of the Chemical and Environmental Technology Center (CQMA) - IPEN-CNEN/SP. (author)

  15. Regulation evolution in Sweden with emphasis on financial aspects of decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Lindskog, St. [the Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Sjoblomb, R. [Tekedo AB, Nykoping (Sweden)

    2008-07-01

    It is generally agreed that it should be the polluters that pay. A corollary to this principle is that it is those who benefit from e g nuclear electricity generation that should pay all the future costs for decommissioning and waste management. In order for such a corollary to be implemented in practice it is necessary that costs can be estimated, that appropriate funds can be accumulated, and that money can be made available at the time when it is needed. This is the principle underlying the recent (2006) recommendation of the European Union Commission on financial resources for decommissioning. The Commission states that a segregated fund with appropriate controls on use is the preferred option for all nuclear installations, and a clear recommendation to this effect is made for new installations. Furthermore, as regards the estimation of decommissioning costs, the Commission recommends a prudent calculation of costs based on appropriate risk management criteria and external supervision. The commission finds that experience shows that exchange of information between national experts concerning the various approaches to and financial arrangements for decommissioning and waste management is an excellent way of facilitating a common response to safety challenges. However, stringent requirements on assessing and securing assets for liabilities have been in force since many years through the various national implementations of the International Financial Reporting Standards (IFRS) and the International Accounting Standards (IAS). Thus, precise calculations are to be presented each year (except for ongoing court cases), and in case estimation is difficult, various scenarios should be considered and a weighed average presented. In Sweden, the Law of Finance (SFS 2006:647) regulates how the costs for decommissioning and waste management are to be calculated and paid. A fee is levied on the use of nuclear electricity and accumulated in the waste fund. In addition, the

  16. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  17. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, T. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2014-09-24

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  18. KIT competence center for decommissioning. Innovation and promotion of trainees; Kompetenzzentrum Rueckbau am KIT. Nachwuchsfoerderung und Innovationen fuer den Rueckbau

    Energy Technology Data Exchange (ETDEWEB)

    Gentes, Sascha [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Inst. fuer Technologie und Management im Baubetrieb

    2016-03-15

    The safe decommissioning of nuclear installations is technically feasible, but is also still a challenge for science, technology and industry. The expertise and know how for decommissioning must be ensured because it will be needed for further decades. Already in 2008 the Karlsruhe Institute of Technology (KIT) had identified this challenge that later emerged through the closure of nuclear power plants in Germany. The KIT opened the professorship Technology and Management of the Decommissioning of Nuclear Installations. In 2014, this section was extended through the dismantling of conventional installations.

  19. Fatores de correção para perímetro escrotal ao sobreano para tourinhos mestiços Aberdeen Angus x Nelore Adjustment factors for scrotal circumference at yearling for crossbred Aberdeen Angus x Nelore young bulls

    Directory of Open Access Journals (Sweden)

    J.S. Lopes

    2009-04-01

    Full Text Available Obtiveram-se fatores de correção (FC para o perímetro escrotal ao sobreano (PES para os efeitos de grupo genético (GG, heterozigose individual (HI, peso ao sobreano (PS e idade do animal à pesagem de sobreano (IDS, utilizando-se registros de peso corporal e medidas de perímetro escrotal obtidos de 11.662 tourinhos das raças Aberdeen Angus, Nelore e de produtos do cruzamento entre elas, criados nas regiões Sul, Sudeste e Centro-Oeste do Brasil, nascidos entre 1987 e 2001. Os coeficientes de regressão que geraram os FC foram estimados pelo método dos quadrados mínimos, adotando um modelo que incluiu os efeitos de grupo de contemporâneos ao sobreano (GC, GG, heterozigose materna (HM, HI, PS e IDS. Todos os efeitos incluídos no modelo foram significativos (PAdjustment factors (AF for scrotal circumference at yearling (SCY were figured out for effects of genetic group (GG, individual heterozygosis (IH, yearling weight (YW, and age of the animal at yearling weight (AYW using body weight and scrotal circumference records from 11,662 Aberdeen Angus, Nelore, and their crosses. The animals were born from 1987 to 2001 and were raised in the South East and Central West Regions of Brazil. The regression coefficients to obtain AF were estimated by least squares means method. The model included the fixed effects of contemporaneous group at yearling (CG, maternal heterozygosis (MH, IH, and the covariates YW (linear and quadratic effects and AYW (linear effect. All the factors included in the model showed significant effects (P<0.01 on SCY. The mean and standard deviation for SCY were 29.90±3.55cm. Quadratic effect of YW on SCY was also observed. Decreases in SCY with the increase in YW was found. High SCY was observed immediately after post-weaning. The YW effects on SCY were 0.06695804±0.00345000cm/kg (linear effect and -0.00005252±0.00000508cm/kg² (quadratic effect. The AYW linear effect on SCY was 0.02176450±0.00038568cm/day. The factors

  20. Photometric Studies of Rapidly Spinning Decommissioned GEO Satellites

    Science.gov (United States)

    Ryan, W.; Ryan, E.

    A satellites general characteristics can be substantially influenced by changes in the space environment. Rapidly spinning decommissioned satellites provide an excellent opportunity to study the rotation-dependent physical processes that affect a resident space objects (RSO) spin kinematics over time. Specifically, inactive satellites at or near geosynchronous Earth-orbit (GEO) provide easy targets for which high quality data can be collected and analyzed such that small differences can be detected under single-year or less time frames. Previous workers have shown that the rotational periods of defunct GEOs have been changing over time [1]. Further, the Yarkovsky-OKeefe-Radzievskii-Paddak (YORP) effect, a phenomenon which has been well-studied in the context of the changing the spin states of asteroids, has recently been suggested to be the cause of secular alterations in the rotational period of inactive satellites [2]. Researchers at the Magdalena Ridge Observatory 2.4-meter telescope (operated by the New Mexico Institute of Mining and Technology) have been investigating the spins states of retired GEOs and other high altitude space debris since 2007 [3]. In this current work, the 2.4-meter telescope was used to track and observe the objects typically over a one- to two-hour period, repeated several times over the course of weeks. When feasible, this is then repeated on a yearly basis. Data is taken with a 1 second cadence, nominally in groups of three 600 second image sets. With the current equipment, the cadence of the image sequences is very precise while the start time is accurate only to the nearest second. Therefore, periods are determined individually using each image sequence. Repeatability of the period determination for each of these sequences is typically on the order of 0.01 second or better for objects where a single period is identified. Spin rate periods determined from the GEO light curves collected thus far have been found to range from ~3 sec to

  1. 77 FR 58591 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

    Science.gov (United States)

    2012-09-21

    ... Burial Facilities AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment... document entitled: NUREG-1307 Revision 15, ``Report on Waste Burial Charges: Changes in Decommissioning... a document is referenced. The NUREG-1307, Revision 15 is available electronically under...

  2. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  3. Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

    1979-01-01

    Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)

  4. 75 FR 43158 - Amended Record of Decision for the Decommissioning of Eight Surplus Production Reactors at the...

    Science.gov (United States)

    2010-07-23

    ... resources, ecological resources, and cumulative impacts. Preliminary calculations (based on near-term... ecological resources impacts were identified in the Supplement Analysis relevant to decommissioning... were issued. New engineering controls (such as development and deployment of robotics in an array...

  5. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  6. Aberdeen Group:视频分析技术推动实体安防发展

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    Harte—Hanks旗下的美国权威市场调研机构Aberdeen Group发布了一项名为“用IT技术武装双眼:视频分析如何走进实体安防”的新研究。研究表明,在不增加全职人员的条件下,性能最好的系统所能处理的摄像机数目和报警信号,比安保人员进行判断分别多出3.3倍和21倍。通过对诸如视频分析等技术的投入,每台摄像机的费用降低了67%,并且比安保人员每天监测、排序和处理的警报多5倍以上。

  7. Ground-water flow and the potential effects of remediation at Graces Quarters, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Tenbus, F.J.; Fleck, W.B.

    1996-01-01

    Ground water in the east-central part of Graces Quarters, a former open-air chemical-agent test facility at Aberdeen Proving Ground, Maryland, is contaminated with chlorinated volatile organic compounds. The U.S. Geological Survey's finite- difference model was used to help understand ground-water flow and simulate the effects of alternative remedial actions to clean up the ground water. Scenarios to simulate unstressed conditions and three extraction well con- figurations were used to compare alternative remedial actions on the contaminant plume. The scenarios indicate that contaminants could migrate from their present location to wetland areas within 10 years under unstressed conditions. Pumping 7 gal/min (gallons per minute) from one well upgradient of the plume will not result in containment or removal of the highest contaminant concentrations. Pumping 7 gal/min from three wells along the central axis of the plume should result in containment and removal of dissolved contami- nants, as should pumping 7 gal/min from three wells at the leading edge of the plume while injecting 7 gal/min back into an upgradient well.

  8. Temporal and vertical variation of hydraulic head in aquifers in the Edgewood area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Donnelly, Colleen A.; Tenbus, Fredrick J.

    1998-01-01

    Water-level data and interpretations from previous hydrogeological studies conducted by the U.S. Geological Survey in the Edgewood Area of Aberdeen Proving Ground (APG), Maryland, were compared to determine similarities and differences among the aquifers. Because the sediments that comprise the shallow aquifers are discontinuous, the shallow ground-water-flow systems are local rather than extensive across the Edgewood Area. Hydrogeologic cross sections, hydrographs of water levels, and vertical gradients calculated from previous studies in the Canal Creek area, Graces Quarters, the O-Field area, Carroll Island, and the J-Field area, over periods of record ranging from 1 to 10 years during 1986-97, were used to determine recharge and discharge areas, connections between aquifers, and hydrologic responses of aquifers to natural and anthropogenic stress. Each of the aquifers in the study areas exhibited variation of hydraulic head that was attributed to seasonal changes in recharge. Upward hydraulic gradients and seasonal reversals of vertical hydraulic gradients between aquifers indicate the potential for local ground-water discharge from most of the aquifers that were studied in the Edgewood Area. Hydraulic head in individual aquifers in Graces Quarters and Carroll Island responded to offsite pumping during part of the period of record. Hydraulic head in most of the confined aquifers responded to tidal loading effects from nearby estuaries.

  9. Evaluation of depleted uranium in the environment at Aberdeen Proving Grounds, Maryland and Yuma Proving Grounds, Arizona. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, P.L.; Clements, W.H.; Myers, O.B.; Bestgen, H.T.; Jenkins, D.G. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Fishery and Wildlife Biology

    1995-01-01

    This report represents an evaluation of depleted uranium (DU) introduced into the environment at the Aberdeen Proving Grounds (APG), Maryland and Yuma Proving Grounds (YPG) Arizona. This was a cooperative project between the Environmental Sciences and Statistical Analyses Groups at LANL and with the Department of Fishery and Wildlife Biology at Colorado State University. The project represents a unique approach to assessing the environmental impact of DU in two dissimilar ecosystems. Ecological exposure models were created for each ecosystem and sensitivity/uncertainty analyses were conducted to identify exposure pathways which were most influential in the fate and transport of DU in the environment. Research included field sampling, field exposure experiment, and laboratory experiments. The first section addresses DU at the APG site. Chapter topics include bioenergetics-based food web model; field exposure experiments; bioconcentration by phytoplankton and the toxicity of U to zooplankton; physical processes governing the desorption of uranium from sediment to water; transfer of uranium from sediment to benthic invertebrates; spead of adsorpion by benthic invertebrates; uptake of uranium by fish. The final section of the report addresses DU at the YPG site. Chapters include the following information: Du transport processes and pathway model; field studies of performance of exposure model; uptake and elimination rates for kangaroo rates; chemical toxicity in kangaroo rat kidneys.

  10. Environmental geophysics of the Pilot Plant on the west branch of Canal Creek, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    McGinnis, L.D.; Miller, S.F.; Daudt, C.R.; Thompson, M.D.; Borden, H.; Benson, M. [Argonne National Lab., IL (United States). Reclamation Engineering and Geosciences Section; Wrobel, J. [Directorate of Safety, Health, and Environment, Aberdeen Proving Ground, MD (United States)

    1994-05-01

    Plans to demolish and remediate the Pilot Plant complex in the Edgewood Area of Aberdeen Proving Ground have served to initiate a series of nonintrusive, environmental-geophysical studies. The studies are assisting in the location and identification of pipes, tanks, trenches, and liquid waste in the subsurface. Multiple databases have been integrated to provide support for detection of underground utilities and to determine the stratigraphy and lithology of the subsurface. The studies were conducted within the double security fence and exterior to the double fence, down gradient toward the west branch of Canal Creek. To determine if contaminants found in the creek were associated with the Pilot Plant, both the east and west banks were included in the study area. Magnetic, conductivity, inductive emf, and ground-penetrating-radar anomalies outline buried pipes, trenches, and various pieces of hardware associated with building activities. Ground-penetrating-radar imagery also defines a paleovalley cut 30 ft into Potomac Group sediments of Cretaceous age. The paleovalley crosses the site between Building E5654 and the Pilot Plant fence. The valley is environmentally significant because it may control the pathways of contaminants. The Pilot Plant complex was used to manufacture CC2 Impregnite and incapacitating agents; it also served as a production facility for nerve agents.

  11. Evaluation of activated nuclides for Fugen Nuclear Power Station's decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Shiratori, Yoshitake; Kawagoe, Shinji; Matsui, Yuji; Higashiura, Norikazu [Japan Nuclear Cycle Development Inst., Tsuruga Head Office, Tsuruga, Fukui (Japan); Iwasaki, Seiji [Nuclear Energy System Inc., Tokyo (Japan)

    2002-09-01

    The density and amount of radioactive nuclides in equipment or concrete including the reactor core need to be evaluated for the decommissioning of the Fugen Nuclear Power Station. To prepare for decommissioning, measurement and evaluation of the neutron flux density have been executed mainly during the reactor operation, because neutron flux density is measured under that condition. Activation evaluation is mainly executed by the calculation method, and the results are checked by the sampling measurements. All of the equipments is divided into three parts, inner core part, shielding part, outer shielding part. The neutron flux distribution of two former parts can be evaluated by calculation, but the last part cannot; it is evaluated by measuring the activation foil for many points. These evaluation methods are checked by a small number of sampling measurements. (author)

  12. Summary of some Recent Work on Financial Planning for Decommissioning of Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lindskog, Staffan (Swedish Nuclear Power Inspectorate, Stockholm (Sweden)); Sjoeblom, Rolf (Tekedo AB, Nykoeping (Sweden))

    2008-06-15

    The new European Union Environmental Liability Directive (ELD) together with the new standard and the increased awareness of the implications of the statements on Environmental liabilities in the IFRS/IA high-light the need for appropriate planning for decommissioning including cost estimations and waste fund management. These new regulations and standards are in some respects more stringent than the strictly nuclear rules. Consequently, The Swedish Nuclear Power Inspectorate has sought communication with non-nuclear actors in the area, including the participation in the recent meeting Environmental Economics and Investment Assessment 11, 27-30 May, 2008, Cadiz, Spain. The present compilation of publications on decommissioning and associated cost calculations in Sweden was prompted by these contacts. The compilation comprises 14 reports published during the last four years

  13. Engineering studies for the Surplus Production Reactor Decommissioning Project at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Miller, R.L.; Powers, E.W. [Westinghouse Hanford Co., Richland, WA (United States); Usher, J.M. [Ebasco Services, Inc., Augusta, GA (United States); Yannitell, D.M. [Ebasco Services, Inc., Oak Ridge, TN (United States)

    1993-10-01

    In 1942, the Hanford Site (near Richland, WA) was commissioned as a facility for the production of plutonium. On location there are nine water cooled, graphite-moderated plutonium production reactors, which are now retired from service. Because the reactors contain irradiated reactor components, and because the buildings that house the reactors are contaminated with low levels of reactivity, the DOE has determined that there is a need for action and that some form of decommissioning or continued surveillance and maintenance is necessary. This report discusses assessments of the alternatives which have determined that while continued surveillance and maintenance adequately isolates remaining radioactive materials from the environment and properly protects human health and safety; decontamination and decommissioning (D&D) will ultimately be necessary. The project is technically complex and will likely be designated as a Department of Energy (DOE) Major System Acquisition or Major Project.

  14. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, Lydia Ilaiza, E-mail: lydiailaiza@gmail.com; Ryong, Kim Tae [KEPCO International Nuclear Graduate School (KINGS) 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 689-882 (Korea, Republic of)

    2015-04-29

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  15. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    Science.gov (United States)

    Saleh, Lydia Ilaiza; Ryong, Kim Tae

    2015-04-01

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  16. Investigation of the responsibility for decommissioning of the Ranstad plant; Utredning av ansvaret foer Ranstadsverkets avveckling

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Haakan; Grundfelt, Bertil [Kemakta Konsult AB, Stockholm (Sweden); Froeberg, Magnus [Froeberg och Lundholm Advokatbyraa AB, Stockholm (Sweden)

    2010-11-15

    The issue of decommissioning, including demolition, of the nuclear facility at the Ranstad plant was raised gradually during 2006-2008. It was then found that it was unclear which company or companies that could be responsible for this decommissioning, economically as well as for the implementation. During this time and until the end of 2009, the concerned authorities, notably Swedish Nuclear Power Inspectorate and SSM, collected a large amount of facts as a basis for assessing liability. This material now needed to be systematized and compiled in order to effectively be utilized in such an assessment. SSM also thought that it would be helpful if an independent party with experience in similar issues could contribute to the interpretation of the legal situation. These were the given conditions of the mission which Kemakta Konsult AB, with the assistance of lawyer Magnus Froeberg, were given by SSM in the autumn of 2009. The results are presented in this final report.

  17. An overview of plutonium-238 decontamination and decommissioning (D and D) projects at Mound

    Energy Technology Data Exchange (ETDEWEB)

    Bond, W.H.; Davis, W.P.; Draper, D.G.; Geichman, J.R.; Harris, J.C.; Jaeger, R.R.; Sohn, R.L.

    1987-01-01

    Mound is currently decontaminating for restricted reuse and/or decommissioning for conditional release four major plutonium-238 contaminated facilities that contained 1700 linear feet of gloveboxes and associated equipment and services. Several thousand linear feet of external underground piping, associated tanks, and contaminated soil are being removed. Two of the facilities contain ongoing operations and will be reused for both radioactive and nonradioactive programs. Two others will be completely demolished and the land area will become available for future DOE building sites. An overview of the successful techniques and equipment used in the decontamination and decommissioning of individual pieces of equipment, gloveboxes, services, laboratories, sections of buildings, entire buildings, and external underground piping, tanks, and soil in a highly populated residential area is described and pictorially presented.

  18. Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).

  19. 2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site, July 2016

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, Brian [USDOE Office of Legacy Management, Washington, DC (United States); Miller, Michele [Navarro Research and Engineering, Oak Ridge, TN (United States)

    2016-07-01

    This report presents the findings of the annual inspection and radiological survey of the Piqua, Ohio, Decommissioned Reactor Site (site). The decommissioned nuclear power demonstration facility was inspected and surveyed on April 15, 2016. The site, located on the east bank of the Great Miami River in Piqua, Ohio, was in fair physical condition. There is no requirement for a follow-up inspection, partly because City of Piqua (City) personnel participated in a March 2016 meeting to address reoccurring safety concerns. Radiological survey results from 104 locations revealed no removable contamination. One direct beta activity reading in a floor drain on the 56-foot level (1674 disintegrations per minute [dpm]/100 square centimeters [cm2]) exceeded the minimum detectable activity (MDA). Beta activity has been detected in the past at this floor drain. The reading was well below the action level of 5000 dpm/100 cm2.

  20. Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)

    Energy Technology Data Exchange (ETDEWEB)

    M.Krug, R.Shogan

    2004-09-01

    Pressurized water reactor (PWR) cores operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs requires detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel (internals) subjected to such conditions. This project studied the effects of reactor service on the mechanical and corrosion properties of samples of baffle plate, former plate, and core barrel from a decommissioned PWR.

  1. Cost calculations for decommissioning and dismantling of nuclear research facilities, Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Inga [StudsvikNuclear AB (Sweden); Backe, S. [Institute for Energy Technology (Norway); Iversen, Klaus [Danish Decommissioning (Denmark); Lindskog, S [Swedish Nuclear Power Inspectorate (Sweden); Salmenhaara, S. [VTT Technical Research Centre of Finland (Finland); Sjoeblom, R. [Tekedo AB (Sweden)

    2006-11-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility. However, no actual international guideline on cost calculations exists at present. Intuitively, it might be tempting to regard costs for decommissioning of a nuclear facility as similar to those of any other plant. However, the presence of radionuclide contamination may imply that the cost is one or more orders of magnitude higher as compared to a corresponding inactive situation, the actual ratio being highly dependent on the level of contamination as well as design features and use of the facility in question. Moreover, the variations in such prerequisites are much larger than for nuclear power plants. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological and other prerequisites. Application of inadequate methodologies especially at early stages has often lead to large underestimations. The goals of the project and the achievements described in the report are as follows: 1) Advice on good practice with regard to: 1a) Strategy and planning; 1b) Methodology selection; 1c) Radiological surveying; 1d) Uncertainty analysis; 2) Techniques for assessment of costs: 2a) Cost structuring; 2b) Cost estimation methodologies; 3) Compilation of data for plants, state of planning, organisations, etc.; 3a) General descriptions of relevant features of the nuclear research facilities; 3b) General plant specific data; 3c) Example of the decommissioning of the R1 research reactor in Sweden; 3d) Example of the decommissioning of the DR1 research reactor in Denmark. In addition, but not described in the present report, is the establishment of a Nordic network in the area including an internet based expert system. It should be noted that the project is planned to exist for at least three years and that the present report is an interim one

  2. Decommissioning of the BR3 PWR[1997 Scientific Report of the Belgian Nuclear Research Centre

    Energy Technology Data Exchange (ETDEWEB)

    Massaut, V.

    1998-07-01

    The dismantling and the decommissioning of nuclear installations at the end of their life-cycle is a new challenge to the nuclear industry. Different techniques and procedures for the dismantling of a nuclear power plant on an existing installation, the BR-3 pressurized-water reactor, are described. The scientific program, objectives, achievements in this research area at the Belgian Nuclear Research Centre SCK-CEN for 1997 are summarized.

  3. Introduction to Decommissioning of Plutonium Production Reactors%钚生产堆退役简介

    Institute of Scientific and Technical Information of China (English)

    王永仙; 安凯媛; 刘东

    2013-01-01

      简要阐述几个国家钚生产堆的退役情况,以期对我国今后生产堆的退役提供借鉴。%  The paper provides briefly the information on the decommissiong of plutonium production reactors in several countries across the world and some suggestions for possible future decommissioning of production reac -tors in our country .

  4. Decontamination and decommissioning surveillance and maintenance report for FY 1991. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D&D) Program has three distinct phases: (1) surveillance and maintenance (S&M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D&D is devoted to S&M at each of the sites. Our S&M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S&M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  5. Renewables-to-reefs? - Decommissioning options for the offshore wind power industry.

    Science.gov (United States)

    Smyth, Katie; Christie, Nikki; Burdon, Daryl; Atkins, Jonathan P; Barnes, Richard; Elliott, Michael

    2015-01-15

    The offshore wind power industry is relatively new but increasing globally, hence it is important that the whole life-cycle is managed. The construction-operation-decommissioning cycle is likely to take 20-30 years and whilst decommissioning may not be undertaken for many years, its management needs to be addressed in both current and future marine management regimes. This can be defined within a Drivers-Activities-Pressures-State Changes-Impacts (on human Welfare)-Responses framework. This paper considers the main decommissioning options - partial or complete removal of all components. A SWOT analysis shows environmental and economic benefits in partial as opposed to complete removal, especially if habitat created on the structures has conservation or commercial value. Benefits (and repercussions) are defined in terms of losses and gains of ecosystem services and societal benefits. The legal precedents and repercussions of both options are considered in terms of the 10-tenets of sustainable marine management. Finally a 'renewables-to-reefs' programme is proposed.

  6. Development of a Multi-Arm Mobile Robot for Nuclear Decommissioning Tasks

    Directory of Open Access Journals (Sweden)

    Mohamed J. Bakari

    2008-11-01

    Full Text Available This paper concerns the design of a two-arm mobile delivery platform for application within nuclear decommissioning tasks. The adoption of the human arm as a model of manoeuvrability, scale and dexterity is the starting point for operation of two seven-function arms within the context of nuclear decommissioning tasks, the selection of hardware and its integration, and the development of suitable control methods. The forward and inverse kinematics for the manipulators are derived and the proposed software architecture identified to control the movements of the arm joints and the performance of selected decommissioning tasks. We discuss the adoption of a BROKK demolition machine as a mobile platform and the integration with its hydraulic system to operate the two seven-function manipulators separately. The paper examines the modelling and development of a real-time control method using Proportional-Integral-Derivative (PID and Proportional-Integral-Plus (PIP control algorithms in the host computer with National Instruments functions and tools to control the manipulators and obtain feedback through wireless communication. Finally we consider the application of a third party device, such as a personal mobile phone, and its interface with LabVIEW software in order to operate the robot arms remotely.

  7. Environmental assessment for decontaminating and decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-01

    The Department of Energy has prepared an environmental assessment on the proposed decontamination and decommissioning of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pennsylvania. Based on the environmental assessment, which is available to the public on request, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969, 42 USC 4321 et seq. Therefore, no environmental impact statement is required. The proposed action is to decontaminate and decommission the Westinghouse Advanced Reactors Division fuel fabrication facilities (the Plutonium Laboratory - Building 7, and the Advanced Fuels Laboratory - Building 8). Decontamination and decommissioning of the facilities would require removal of all process equipment, the associated service lines, and decontamination of the interior surfaces of the buildings so that the empty buildings could be released for unrestricted use. Radioactive waste generated during these activities would be transported in licensed containers by truck for disposal at the Department's facility at Hanford, Washington. Useable non-radioactive materials would be sold as excess material, and non-radioactive waste would be disposed of by burial as sanitary landfill at an approved site.

  8. The final status of the decommissioning of research reactors in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Hong, S. B.; Park, J. H.; Chung, U. S. [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of)

    2010-10-15

    A decommissioning project for the Korean Research Reactors (KRR-1 and 2) was started in 1997 and had been carried out with the goal of completion being by the end of 2008. All the facilities were dismantled and the building surfaces decontaminated. The radioactive waste was packed into 200 liter drums and 4 m{sup 3} containers and temporarily stored on site until their final disposal at the national repository facility. Some of the releasable waste was freely released and utilized for the non-nuclear industries. The assessment of the residual radioactivity was carried out according to Multi Agency Radiation Site Survey and Investigation Manual guidance, and accordingly, the safety of the site release was verified. The site and the buildings will be cleared for a reuse for non nuclear purposes after a review of the assessment. In this paper, the final status of the decommissioning of research reactors in Korea including dismantlement processes, waste management and a final assessment for unrestricted use of the site and buildings for the final goal of the decommissioning project that will be described. (Author)

  9. Technology, safety, and costs of decommissioning a reference pressurized water reactor power station

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

    1978-05-01

    Safety and cost information was developed for the conceptual decommissioning of a large (1175 MW(e)) pressurized water reactor (PWR) power station. Two approaches to decommissioning, Immediate Dismantlement and Safe Storage with Deferred Dismantlement, were studied to obtain comparisons between costs, occupational radiation doses, potential radiation dose to the public, and other safety impacts. Immediate Dismantlement was estimated to require about six years to complete, including two years of planning and preparation prior to final reactor shutdown, at a cost of $42 million, and accumulated occupational radiation dose, excluding transport operations, of about 1200 man-rem. Preparations for Safe Storage were estimated to require about three years to complete, including 1/sup 1///sub 2/ years for planning and preparation prior to final reactor shutdown, at a cost of $13 million and an accumulated occupational radiation dose of about 420 man-rem. The cost of continuing care during the Safe Storage period was estimated to be about $80 thousand annually. Accumulated occupational radiation dose during the Safe Storage period was estimated to range from about 10 man-rem for the first 10 years to about 14 man-rem after 30 years or more. The cost of decommissioning by Safe Storage with Deferred Dismantlement was estimated to be slightly higher than Immediate Dismantlement. Cost reductions resulting from reduced volumes of radioactive material for disposal, due to the decay of the radioactive containments during the deferment period, are offset by the accumulated costs of surveillance and maintenance during the Safe Storage period.

  10. Lessons Learned Following the Successful Decommissioning of a Reaction Vessel Containing Lime Sludge and Technetium-99

    Energy Technology Data Exchange (ETDEWEB)

    Dawson, P. M.; Watson, D. D.; Hylko, J. M.

    2002-02-25

    This paper documents how WESKEM, LLC utilized available source term information, integrated safety management, and associated project controls to safely decommission a reaction vessel and repackage sludge containing various Resource Conservation and Recovery Act constituents and technetium-99 (Tc-99). The decommissioning activities were segmented into five separate stages, allowing the project team to control work related decisions based on their knowledge, experience, expertise, and field observations. The information and experience gained from each previous stage and rehearsals contributed to modifying subsequent entries, further emphasizing the importance of developing hold points and incorporating lessons learned. The hold points and lessons learned, such as performing detailed personal protective equipment (PPE) inspections during sizing and repackaging operations, and using foam-type piping insulation to prevent workers from cutting or puncturing their PPE on sharp edge s or small shards generated during sizing operations, minimized direct contact with the Tc-99. To prevent the spread of contamination, the decommissioning activities were performed inside a containment enclosure connected to negative air machines. After performing over 235 individual entries totaling over 285 project hours, only one first aid was recorded during this five-stage project.

  11. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

  12. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  13. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  15. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  16. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  17. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-15

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities.

  18. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

  19. Características da carcaça de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos terminados em confinamento Carcass traits of Canchim, Aberdeen Angus and reciprocal crosses finished in confinement

    Directory of Open Access Journals (Sweden)

    Daniel Perotto

    1999-06-01

    Full Text Available Foram analisadas quatorze características quantitativas das carcaças de 137 machos bovinos inteiros pertencentes aos grupos Canchim (Ca, Aberdeen Angus (Ab, 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab e 5/8Ab+3/8Ca, nascidos na Estação Experimental Fazenda Modelo, em Ponta Grossa-PR, no período de 1988 a 1993. As médias para a idade e para o peso ao início do confinamento, duração do confinamento, idade e peso ao abate foram, respectivamente, 737 dias, 356kg, 97 dias, 834 dias e 468kg. Durante o confinamento, os garrotes receberam silagem de milho à vontade mais uma ração concentrada (79% de NDT, 17,8% de PB fornecida à base de 1% do peso vivo do animal por dia. Os grupos Ca e Ab diferiram entre si para todas as características, exceto para percentagem de costilhar (PEC. O Ca foi superior ao Ab para peso de carcaça quente (PCQ, rendimento de carcaça quente (RCQ, área de olho de lombo (AOL, conformação, percentagem de músculos (PEM, peso da porção comestível da carcaça (PPC e peso de carcaça quente por dia de vida ao abate (PCQ/DDV. O Ab superou o Ca quanto à espessura de gordura de cobertura (ECG e à percentagem de gordura (PEG. Houve heterose para PCQ, RCQ, AOL, PPC e PCQ/DDV. As duas gerações avançadas de cruzamentos alternados Ca x Ab apresentaram desempenho superior à média das raças paternas para PCQ, RCQ, AOL, PPC e PCQ/DDV. O desempenho de um esquema alternado de cruzamentos entre Ca e Ab seria melhor que o de qualquer dessas duas criada isoladamente.Fourteen quantitative carcass traits of 137 Canchim; 5/8 Charolais + 3/8 Zebu, (Ca, Aberdeen Angus (Ab, 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab and 5/8Ab+3/8Ca, born at Est. Exp. Fazenda Modelo, in Ponta Grossa-PR, Brazil, from 1988 to 1993, were analyzed. Averages for age at beginning of confinement, initial weight, length of confinement period, final age and final weight were, respectively, 737 days, 356kg, 97 days, 834 days and 468kg. During the confinement period

  20. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project.

  1. Joint U.S./Russian Study on the Development of a Preliminary Cost Estimate of the SAFSTOR Decommissioning Alternative for the Leningrad Nuclear Power Plant Unit #1

    Energy Technology Data Exchange (ETDEWEB)

    SM Garrett

    1998-09-28

    The objectives of the two joint Russian/U.S. Leningrad Nuclear Power Plant (NPP) Unit #1 studies were the development of a safe, technically feasible, economically acceptable decom missioning strategy, and the preliminary cost evaluation of the developed strategy. The first study, resulting in the decommissioning strategy, was performed in 1996 and 1997. The preliminary cost estimation study, described in this report, was performed in 1997 and 1998. The decommissioning strategy study included the analyses of three basic RBM.K decommission- ing alternatives, refined for the Leningrad NPP Unit #1. The analyses included analysis of the requirements for the planning and preparation as well as the decommissioning phases.

  2. Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu [Korea Institute of Construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

  3. Effect of freezing prior to aging on myoglobin redox forms and CIE color of beef from Nellore and Aberdeen Angus cattle.

    Science.gov (United States)

    Aroeira, Carolina Naves; de Almeida Torres Filho, Robledo; Fontes, Paulo Rogério; de Lemos Souza Ramos, Alcinéia; de Miranda Gomide, Lúcio Alberto; Ladeira, Márcio Machado; Ramos, Eduardo Mendes

    2017-03-01

    The objective of this study was to evaluate the effect of freezing prior to wet aging on the color of Nellore and Aberdeen Angus cattle meat. Samples of the Longissimus thoracis muscle were subjected to two treatments: conventional aging (0, 7, 14 and 21days); and freezing (-20°C for 40days) followed by thawing and aging. Freezing promoted (Pcolor of the Nellore meat was less (Pcolor stability in vacuum-packed beef is reduced by freezing prior to aging and that reduction depends on the animal breed.

  4. The Annual Conference on Han-Based Liquid Propellants (5th) Held in Aberdeen Proving Ground on 22-24 August 1989

    Science.gov (United States)

    1990-06-01

    at BRL, Aberdeen, Maryland 1988. 2 Lee P P Thermochimica &.a. i2Z, ppl-16, 1986. Back M H 3 Lee P P Thermochimica Acta 121, pp89-100, 1988. Back M H...4 Gray P Oxidation And Combustion Reviews Z, Lee P R ppl-183, 1967. 5 Townsend D I Thermochimica Acta 7, ppl-30, 1980. Tou J C 6 Townsend D I I. Chem...USA, 1987. 8 Bunyan P F RARDE Memorandum 9/89, 1989. 9 Bunyan P F Thermochimica Acta J3, pp335-344, 1988. 10 Bunyan P F RARDE Memorandum 4/88, 1988. 11

  5. Heterose sobre os pesos de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos

    Directory of Open Access Journals (Sweden)

    PEROTTO DANIEL

    2000-01-01

    Full Text Available O trabalho foi conduzido para estimar a heterose sobre os pesos ao nascimento (PNT, à desmama (P210 e ao ano (P365 e sobre os ganhos de pesos médios diários do nascimento à desmama (G210 e da desmama ao ano (G365 nas quatro primeiras gerações do sistema de cruzamentos alternados entre as raças Canchim (C e Aberdeen Angus (A. Os dados de 1.147 bezerros nascidos de 1981 a 1998 foram analisados pelo método dos mínimos quadrados, ajustando-se um modelo linear que incluiu os efeitos linear e quadrático da idade da mãe do bezerro e os efeitos fixos de sexo, grupo genético, mês e ano de nascimento do bezerro. Estimativas de heterose e de outras diferenças genéticas foram estimadas por contrastes entre médias e testadas pelo teste t. O contraste "CA" foi positivo e significativo (P<0,001 para as cinco características. O contraste F1CAF1AC teve sinal negativo e foi altamente significativo (P<0,001 para P210 e G210 e significativo (P<0,05 para P365. A geração F1 exibiu heterose de 4,8% para P210 e de 4,9% para G210. A heterose materna foi de 3,7%, 5,8%, 6,3% e 20,4%, respectivamente, para P210, G210, P365 e G365. A heterose média das terceira e quarta gerações do cruzamento alternado entre C e A foi de 4,6% para P210, 5,3% para G210 e de 3,5% para P365.

  6. Work plan for focused feasibility study of the toxic burning pits area at J-Field, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Biang, C.; Benioff, P.; Martino, L.; Patton, T.

    1995-03-01

    The Environmental Management Division (EMD) of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCIA). J-Field is within the Edgewood Area of APG in Harford County, Maryland. Since World War II, activities in the Edgewood Area have included the development, manufacture, testing, and destruction of chemical agents and munitions. These materials were destroyed at J-Field by open burning and open detonation (OB/OD). Considerable archival information about J-Field exists as a result of efforts by APG staff to characterize the hazards associated with the site. Contamination of J-Field was first detected during an environmental survey of the Edgewood Area conducted in 1977 and 1978 by the US Army Toxic and Hazardous Materials Agency (USATHAMA)(predecessor to the US Army Environmental Center). As part of a subsequent USATHAMA environmental survey, 11 wells were installed and sampled at J-Field. Contamination at J-Field was also detected during a munitions disposal survey conducted by Princeton Aqua Science in 1983. The Princeton Aqua Science investigation involved the installation and sampling of nine wells and the collection and analysis of surficial and deep composite soil samples. In 1986, a Resource Conservation and Recovery Act (RCRA) permit (MD3-21-0021355) requiring a basewide RCRA Facility Assessment (RFA) and a hydrogeologic assessment of J-Field was issued by the US Environmental Protection Agency (EPA). In 1987, the US Geological Survey (USGS) began a two-phased hydrogeologic assessment in which data were collected to model groundwater flow at J-Field. Soil gas investigations were conducted, several well clusters were installed, a groundwater flow model was developed, and groundwater and surface water monitoring programs were established that continue today-

  7. Remedial investigation sampling and analysis plan for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Field Sampling Plan

    Energy Technology Data Exchange (ETDEWEB)

    Benioff, P.; Biang, R.; Dolak, D.; Dunn, C.; Martino, L.; Patton, T.; Wang, Y.; Yuen, C.

    1995-03-01

    The Environmental Management Division (EMD) of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland (Figure 1. 1). Since World War II activities in the Edgewood Area have included the development, manufacture, testing, and destruction of chemical agents and munitions. These materials were destroyed at J-Field by open burning and open detonation (OB/OD). Considerable archival information about J-Field exists as a result of efforts by APG staff to characterize the hazards associated with the site. Contamination of J-Field was first detected during an environmental survey of the Edgewood Area conducted in 1977 and 1978 by the US Army Toxic and Hazardous Materials Agency (USATHAMA) (predecessor to the US Army Environmental Center [AEC]). As part of a subsequent USATHAMA -environmental survey, 11 wells were installed and sampled at J-Field. Contamination at J-Field was also detected during a munitions disposal survey conducted by Princeton Aqua Science in 1983. The Princeton Aqua Science investigation involved the installation and sampling of nine wells and the collection and analysis of surficial and deep composite soil samples. In 1986, a Resource Conservation and Recovery Act (RCRA) permit (MD3-21-002-1355) requiring a basewide RCRA Facility Assessment (RFA) and a hydrogeologic assessment of J-Field was issued by the US Environmental Protection Agency (EPA). In 1987, the US Geological Survey (USGS) began a two-phased hydrogeologic assessment in data were collected to model, groundwater flow at J-Field. Soil gas investigations were conducted, several well clusters were installed, a groundwater flow model was developed, and groundwater and surface water monitoring programs were established that continue today.

  8. Assessment of volatile organic compounds in surface water at West Branch Canal Creek, Aberdeen Proving Ground, Maryland, 1999

    Science.gov (United States)

    Olsen, Lisa D.; Spencer, Tracey A.

    2000-01-01

    The U.S. Geological Survey (USGS) collected 13 surface-water samples and 3 replicates from 5 sites in the West Branch Canal Creek area at Aberdeen Proving Ground from February through August 1999, as a part of an investigation of ground-water contamination and natural attenuation processes. The samples were analyzed for volatile organic compounds, including trichloroethylene, 1,1,2,2-tetrachloroethane, carbon tetrachloride, and chloroform, which are the four major contaminants that were detected in ground water in the Canal Creek area in earlier USGS studies. Field blanks were collected during the sampling period to assess sample bias. Field replicates were used to assess sample variability, which was expressed as relative percent difference. The mean variability of the surface-water replicate analyses was larger (35.4 percent) than the mean variability of ground-water replicate analyses (14.6 percent) determined for West Branch Canal Creek from 1995 through 1996. The higher variability in surface-water analyses is probably due to heterogeneities in the composition of the surface water rather than differences in sampling or analytical procedures. The most frequently detected volatile organic compound was 1,1,2,2- tetrachloroethane, which was detected in every sample and in two of the replicates. The surface-water contamination is likely the result of cross-media transfer of contaminants from the ground water and sediments along the West Branch Canal Creek. The full extent of surface-water contamination in West Branch Canal Creek and the locations of probable contaminant sources cannot be determined from this limited set of data. Tidal mixing, creek flow patterns, and potential effects of a drought that occurred during the sampling period also complicate the evaluation of surface-water contamination.

  9. Hydrogeologic setting, hydraulic properties, and ground-water flow at the O-Field area of Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Banks, W.S.; Smith, B.S.; Donnelly, C.A.

    1996-01-01

    The U.S. Army disposed chemical agents, laboratory materials, and unexploded ordnance at O-Field in the Edgewood area of Aberdeen Proving Ground, Maryland, from before World War II until at least the 1950's. Soil, ground water, surface water,and wetland sediments in the O-Field area were contaminated from the disposal activity. A ground-water-flow model of the O-Field area was constructed by the U.S. Geological Survey (USGS) in 1989 to simulate flow in the central and southern part of the Gunpowder Neck. The USGS began an additional study of the contamination in the O-Field area in cooperation with the U.S. Army in 1990 to (1) further define the hydrogeologic framework of the O-Field area, (2) characterize the hydraulic properties of the aquifers and confining units, and (3) define ground-water flow paths at O-Field based on the current data and simulations of ground-water flow. A water-table aquifer, an upper confining unit, and an upper confined aquifer comprise the shallow ground-water aquifer system of the O-Field area. A lower confining unit, through which ground-water movement is negligible, is considered a lower boundary to the shallow aquifer system. These units are all part of the Pleistocene Talbot Formation. The model developed in the previous study was redesigned using the data collected during this study and emphasized New O-Field. The current steady-state model was calibrated to water levels of June 1993. The rate of ground-water flow calculated by the model was approximately 0.48 feet per day (ft/d) and the rate determined from chlorofluorocarbon dates was approximately 0.39 ft/d.

  10. Ground-water flow and the possible effects of remedial actions at J-Field, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Hughes, W.B.

    1995-01-01

    J-Field, located in the Edgewood Area of Aberdeen Proving Ground, Md, has been used since World War II to test and dispose of explosives, chemical warfare agents, and industrial chemicals resulting in ground-water, surface-water, and soil contami- nation. The U.S. Geological Survey finite-difference model was used to better understand ground-water flow at the site and to simulate the effects of remedial actions. A surficial aquifer and a confined aquifer were simulated with the model. A confining unit separates these units and is represented by leakance between the layers. The area modeled is 3.65 mi2; the model was constructed with a variably spaced 40 X 38 grid. The horizontal and lower boundaries of the model are all no-flow boundaries. Steady-state conditions were used. Ground water at the areas under investigation flows from disposal pit areas toward discharge areas in adjacent estuaries or wetlands. Simulations indicate that capping disposal areas with an impermeable cover effectively slows advective ground water flow by 0.7 to 0.5 times. Barriers to lateral ground-water flow were simulated and effectively prevented the movement of ground water toward discharge areas. Extraction wells were simulated as a way to contain ground-water contamination and to extract ground water for treatment. Two wells pumping 5 gallons per minute each at the toxic-materials disposal area and a single well pumping 2.5 gallons per minute at the riot-control-agent disposal area effectively contained contamination at these sites. A combi- nation of barriers to horizontal flow east and south of the toxic-materials disposal area, and a single extraction well pumping at 5 gallons per minute can extract contaminated ground water and prevent pumpage of marsh water.

  11. Long-term fate of depleted uranium at Aberdeen and Yuma Proving Grounds: Human health and ecological risk assessments

    Energy Technology Data Exchange (ETDEWEB)

    Ebinger, M.H.; Beckman, R.J.; Myers, O.B. [Los Alamos National Lab., NM (United States); Kennedy, P.L.; Clements, W.; Bestgen, H.T. [Colorado State Univ., Ft. Collins, CO (United States). Dept. of Fishery and Wildlife Biology

    1996-09-01

    The purpose of this study was to evaluate the immediate and long-term consequences of depleted uranium (DU) in the environment at Aberdeen Proving Ground (APG) and Yuma Proving Ground (YPG) for the Test and Evaluation Command (TECOM) of the US Army. Specifically, we examined the potential for adverse radiological and toxicological effects to humans and ecosystems caused by exposure to DU at both installations. We developed contaminant transport models of aquatic and terrestrial ecosystems at APG and terrestrial ecosystems at YPG to assess potential adverse effects from DU exposure. Sensitivity and uncertainty analyses of the initial models showed the portions of the models that most influenced predicted DU concentrations, and the results of the sensitivity analyses were fundamental tools in designing field sampling campaigns at both installations. Results of uranium (U) isotope analyses of field samples provided data to evaluate the source of U in the environment and the toxicological and radiological doses to different ecosystem components and to humans. Probabilistic doses were estimated from the field data, and DU was identified in several components of the food chain at APG and YPG. Dose estimates from APG data indicated that U or DU uptake was insufficient to cause adverse toxicological or radiological effects. Dose estimates from YPG data indicated that U or DU uptake is insufficient to cause radiological effects in ecosystem components or in humans, but toxicological effects in small mammals (e.g., kangaroo rats and pocket mice) may occur from U or DU ingestion. The results of this study were used to modify environmental radiation monitoring plans at APG and YPG to ensure collection of adequate data for ongoing ecological and human health risk assessments.

  12. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure, Volume 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N. [Pacific Northwest Lab., Richland, WA (United States)

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1988), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the {prime}978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

  13. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

  14. 30 CFR 285.529 - Can I use a lease- or grant-specific decommissioning account to meet the financial assurance...

    Science.gov (United States)

    2010-07-01

    ... Assurance Requirements Requirements for Financial Assurance Instruments § 285.529 Can I use a lease- or... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Can I use a lease- or grant-specific decommissioning account to meet the financial assurance requirements related to decommissioning? 285.529...

  15. Restoration of contaminated sites in the project PIMIC decommissioning. The case of the lentil; Restauracion de terrenos contaminados en el proyecto PIMIC desmantelamiento. El caso de la lenteja

    Energy Technology Data Exchange (ETDEWEB)

    Medina Tellez, G.

    2010-07-01

    During execution PIMIC Decommissioning Project at CIEMAT has detected the existence of contaminated sites in some parts of the area affected by the project. The inclusion within the scope of this project, decontamination, involves dealing with special challenges, as to what are the decommissioning of contaminated systems and equipment in buildings.

  16. Allowable residual-contamination levels for decommissioning facilities in the 100 areas of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, W.E. Jr.; Napier, B.A.

    1983-07-01

    This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for five generic categories of facilities in the 100 Areas of the Hanford Site. The purpose of this study is to provide ARCL data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. The information on ARCL values for restricted and controlled use provided by this report is intended to permit a full consideration of decommissioning alternatives. ARCL results are presented both for surface contamination remaining in facilities (in dpm/100 cm/sup 2/), and for unconfined surface and confined subsurface soil conditions (in pCi/g). Two confined soil conditions are considered: contamination at depths between 1 and 4 m, and contamination at depths greater than or equal to 5 m. A set of worksheets are presented in an appendix for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations, to consider the impacts of radioactive decay, and to predict instrument responses. Finally, a comparison is made between the unrestricted release ARCL values for the 100 Area facilities and existing decommissioning and land disposal regulations. For surface contamination, the comparison shows good agreement. For soil contamination, the comparison shows good agreement if reasonable modification factors are applied to account for the differences in modeling soil contamination and licensed low-level waste.

  17. Characterization of the Hanford 300 area burial grounds. Final report: decontamination and decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, S.J.; Ames, L.L.; Fitzner, R.E.; Gee, G.W.; Sandness, G.A.; Simmons, C.S.

    1980-01-01

    Pacific Northwest Laboratory conducted a series of investigations at the Hanford Site to develop technologies for characterizing and monitoring radioactive waste burial facilities that could be used in determining appropriate decommissioning alternatives. Specific objectives were to develop unique functional geophysics, geochemical, soil physics, numerical modeling, and biological methodologies needed to better characterize and monitor buried radioactive waste disposal sites. To meet these objectives the project was divided into four tasks: Task I, Geophysical Evaluation - Geophysical surveys were taken to locate and define the gross composition of waste materials. Task II, Geochemical Analysis - The interaction of disposed radionuclides with geologic media was analyzed through an integrated radiochemical procedure. Task III, Fluid Transport and Modeling - Computer modeling of water migration in partially saturated groundwater systems was verified with actual data collected at a field test facility used to monitor micrometeorological and geohydrological energy and mass transfer factors. Task IV, Biological Transport - Several biological organisms were evaluated for potential radionuclide uptake and transport. Along with the four tasks, the project included a review of pertinent literature and regulatory issues that might affect the alternatives selected. Surveys were taken of the surrounding area and specific sites and operations. The overall results indicated that the 300 Area Burial Grounds have been adequate in containing radioactive waste. Based on the results of the project, the alternatives identified for decommissioning these sites are exhumation and translocation, entombment, perpetual care, and abandonment. Perpetual care (currently used) appears to be the best decommissioning alternative for these burial grounds at this time. However, another alternative may be selected depending on future waste management policies, plans, or activities.

  18. Application of in situ measurement for site remediation and final status survey of decommissioning KRR site

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sang Bum; Nam, Jong Soo; Choi, Yong Suk; Seo, Bum Kyoung; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-06-15

    In situ gamma spectrometry has been used to measure environmental radiation, assumptions are usually made about the depth distribution of the radionuclides of interest in the soil. The main limitation of in situ gamma spectrometry lies in determining the depth distribution of radionuclides. The objective of this study is to develop a method for subsurface characterization by in situ measurement. The peak to valley method based on the ratio of counting rate between the photoelectric peak and Compton region was applied to identify the depth distribution. The peak to valley method could be applied to establish the relation between the spectrally derived coefficients (Q) with relaxation mass per unit area (β) for various depth distribution in soil. The in situ measurement results were verified by MCNP simulation and calculated correlation equation. In order to compare the depth distributions and contamination levels in decommissioning KRR site, in situ measurement and sampling results were compared. The in situ measurement results and MCNP simulation results show a good correlation for laboratory measurement. The simulation relationship between Q and source burial for the source layers have exponential relationship for a variety depth distributions. We applied the peak to valley method to contaminated decommissioning KRR site to determine a depth distribution and initial activity without sampling. The observed results has a good correlation, relative error between in situ measurement with sampling result is around 7% for depth distribution and 4% for initial activity. In this study, the vertical activity distribution and initial activity of {sup 137}Cs could be identifying directly through in situ measurement. Therefore, the peak to valley method demonstrated good potential for assessment of the residual radioactivity for site remediation in decommissioning and contaminated site.

  19. Industrial Hygiene Concerns during the Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

    CERN Document Server

    Lumia, M E

    2002-01-01

    A significant industrial hygiene concern during the Decontamination and Decommissioning (D and D) of the Tokamak Fusion Test Reactor (TFTR) was the oxidation of the lead bricks' surface, which were utilized for radiation shielding. This presented both airborne exposure and surface contamination issues for the workers in the field removing this material. This paper will detail the various protection and control methods tested and implemented to protect the workers, including those technologies deployed to decontaminate the work surfaces. In addition, those techniques employed to recycle the lead for additional use at the site will be discussed.

  20. Decommissioning of the ASTRA research reactor: Planning, executing and summarizing the project

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2010-01-01

    Full Text Available The decommissioning of the ASTRA research reactor at the Austrian Research Centres Seibersdorf was described within three technical papers already released in Nuclear Technology & Radiation Protection throughout the years 2003, 2006, and 2008. Following a suggestion from IAEA the project was investigated well after the files were closed regarding rather administrative than technical matters starting with the project mission, explaining the project structure and identifying the key factors and the key performance indicators. The continuous documentary and reporting system as implemented to fulfil the informational needs of stake-holders, management, and project staff alike is described. Finally the project is summarized in relationship to the performance indicators.

  1. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 2 (Appendices) contains the detailed analyses and data needed to support the results given in Volume 1.

  2. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, E. S.; Holter, G. M.

    1980-06-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.

  3. Cutting Technology for Decommissioning of the Reactor Pressure Vessels in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kim, Geun Ho; Moon, Jei Kwon; Choi, Byung Seon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Lots of nuclear power plants have been decommissioned during the last 2 decades. An essential part of this work is the dismantling of the Reactor Pressure Vessel and its Internals. For this purpose a wide variety of different cutting technologies have been developed, adapted and applied. A detailed introduction to Plasma Arc cutting, Contact Arc Metal cutting and Abrasive Water Suspension Jet cutting is given, as it turned out that these cutting technologies are particularly suitable for these type of segmentation work. A comparison of these technologies including gaseous emissions, cutting power, manipulator requirements as well as selected design approaches are given. Process limits as well as actual limits of application are presented

  4. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    Energy Technology Data Exchange (ETDEWEB)

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  5. Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities

    Energy Technology Data Exchange (ETDEWEB)

    Erickson, T.A.

    1998-11-01

    The objectives of this task are to: Develop a model (paper) to estimate the cost and waste generation of cleanup within the Environmental Management (EM) complex; Identify technologies applicable to decontamination and decommissioning (D and D) operations within the EM complex; Develop a database of facility information as linked to project baseline summaries (PBSs). The above objectives are carried out through the following four subtasks: Subtask 1--D and D Model Development, Subtask 2--Technology List; Subtask 3--Facility Database, and Subtask 4--Incorporation into a User Model.

  6. Decontamination and decommissioning project of the TRIGA mark - 2 and 3 research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jung, K. J.; Baik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Kim, J. K.; Lee, D. G.; Kim, H. R.; Lee, B. J.; Yang, S. H.

    2001-01-15

    The decommissioning license for KRR (Korea Research Reactor) 1 and 2 was issued Nov. 23, 2000. The atmospheric stability on the KRR site was evaluated using the meteorological data measured at the site. From the results of this evaluation, the population dose was evaluated for the public who lives at the periphery of the site. The Radiation Safety Management Guideline was developed and it will be used as a base line making Radiation Safety Management Procedure. The container was specially designed and manufactured for the storing of low level radioactive solid waste arising from the D and D activities. Firstly, the 50 containers were completely manufactured.

  7. Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This EA evaluates the proposed action to decontaminate and decommission GA`s hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R&D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required.

  8. Decommissioning of nuclear facilities at the Nuclear Research Institute Rez plc

    Directory of Open Access Journals (Sweden)

    Podlaha Josef

    2010-01-01

    Full Text Available The Nuclear Research Institute Rez has been a leading institution in all areas of nuclear R&D in the Czech Republic since it was established in 1955. After more than 50 years of activities in the field, there are some environmental liabilities that need to be remedied. The remediation of old environmental liabilities concerning the Nuclear Research Institute is the only ongoing decommissioning project in the Czech Republic. The nature of these environmental liabilities is very specific and requires special remediation procedures. The process begun in 2003 and is expected to be finished by 2014.

  9. SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

    2010-01-04

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material

  10. Third party liability of nuclear installation decommissioning with Russian nuclear submarines as an example: insurance versus technologies

    Energy Technology Data Exchange (ETDEWEB)

    Gavrilov, S.D. [PREKSAT Ltd., Moscow (Russian Federation); Derevyankin, A.A. [Reseaarch and Development Institute of Nuclear Power Engineering, Moscow (Russian Federation); Khamyanov, L.P. [All-Russian Research Institute on NPP Operation, Moscow (Russian Federation); Kovalenko, V.N. [Ministry for Nuclear Energy Of Russian, Moscow (Russian Federation); Kovalivich, O.M. [Research and Technological Center for Nuclear and Radiation Safety of Supervisory, Nuclear Energy State Commitee of Russia, Moscow (Russian Federation); Smirnov, P.L. [Nuclear Safety Institute of Russian Academy of Sciences, Moscow (Russian Federation)

    2001-07-01

    Third party and environment of civil liability damage caused by incidents at military nuclear installations, for instance at decommissioned NPS (nuclear powered submarines), may be divided into three main trends: -) Liability of NPS without high-enriched irradiated nuclear fuel (SNF) for its self-submersion (radiation incident); -) Liability of NPS with SNF aboard for its self-submersion (radiation incident); and -) Liability of floating NPS for its SNF discharge (nuclear accident). Without step-by-step transition from the Russian Federation guaranties to insurance and making allowance for liability limits according to the Vienna Convention approach, the sizes of the financial guarantee for the civil liability of the NPS owner (Russian state), in US dollars of 2000, are approximately assessed as the following: -) storing decommissioned NPS or a floating module without SNF - from 12 to 25 thousand dollars per year (per one submarine or module); -) storing decommissioned NPS with SNF inside reactors cores - from 25 to 40 thousand dollars per year; -) assembly-by-assembly removing SNF from reactors' core of decommissioned NPS - up to 1.5 million dollars for undamaged reactor per the discharging period; -) SNF removing within reactor using the filled in-space reactor's core by liquid-phased hardened or dispersed solid-phase materials from decommissioned NPS - from 30 to 50 thousand dollars for undamaged reactor per the discharging period. Both rates and sums for NPS with damaged reactors are to be estimated for the each damaged reactor and NPS at all. It is necessary to perform the measures reducing the risk of nuclear accidents of NPS with undamaged SNF and NPS with damaged reactors in possibly short time. It will allow not only to cut risks by ten times and more, but also to accumulate necessary insurance reserves faster. These measures can be partially or completely executed using the preventing measures reserves assigned to all decommissioned Russian NPS

  11. Optimization of ground-water withdrawal at the old O-Field area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Banks, William S.L.; Dillow, Jonathan J.A.

    2001-01-01

    The U.S. Army disposed of chemical agents, laboratory materials, and unexploded ordnance at the Old O-Field landfill at Aberdeen Proving Ground, Maryland, beginning prior to World War II and continuing until at least the 1950?s. Soil, ground water, surface water, and wetland sediments in the Old O-Field area were contaminated by the disposal of these materials. The site is in the Atlantic Coastal Plain, and is characterized by a complex series of Pleistocene and Holocene sediments formed in various fluvial, estuarine, and marine-marginal hydrogeologic environments. A previously constructed transient finite-difference ground-water-flow model was used to simulate ground-water flow and the effects of a pump-and-treat remediation system designed to prevent contaminated ground water from flowing into Watson Creek (a tidal estuary and a tributary to the Gunpowder River). The remediation system consists of 14 extraction wells located between the Old O-Field landfill and Watson Creek.Linear programming techniques were applied to the results of the flow-model simulations to identify optimal pumping strategies for the remediation system. The optimal management objective is to minimize total withdrawal from the water-table aquifer, while adhering to the following constraints: (1) ground-water flow from the landfill should be prevented from reaching Watson Creek, (2) no extraction pump should be operated at a rate that exceeds its capacity, and (3) no extraction pump should be operated at a rate below its minimum capacity, the minimum rate at which an Old O-Field pump can function. Water withdrawal is minimized by varying the rate and frequency of pumping at each of the 14 extraction wells over time. This minimizes the costs of both pumping and water treatment, thus providing the least-cost remediation alternative while simultaneously meeting all operating constraints.The optimal strategy identified using this objective and constraint set involved operating 13 of the 14

  12. Assessment of volatile organic compounds in surface water at Canal Creek, Aberdeen Proving Ground, Maryland, November 1999-September 2000

    Science.gov (United States)

    Phelan, Daniel J.; Olsen, Lisa D.; Senus, Michael P.; Spencer, Tracey A.

    2001-01-01

    The purpose of this report is to describe the occurrence and distribution of volatile organic compounds in surface-water samples collected by the U.S. Geological Survey in the Canal Creek area of Aberdeen Proving Ground, Maryland, from November 1999 through September 2000. The report describes the differences between years with below normal and normal precipitation, the effects of seasons, tide stages, and location on volatile organic compound concentrations in surface water, and provides estimates of volatile organic concentration loads to the tidal Gunpowder River. Eighty-four environmental samples from 20 surface-water sites were analyzed. As many as 13 different volatile organic compounds were detected in the samples. Concentrations of volatile organic compounds in surface-water samples ranged from below the reporting limit of 0.5 micrograms per liter to a maximum of 50.2 micrograms per liter for chloroform. Chloroform was detected most frequently, and was found in 55 percent of the environmental samples that were analyzed for volatile organic compounds (46 of 84 samples). Carbon tetrachloride was detected in 56 percent of the surface-water samples in the tidal part of the creek (34 of 61 samples), but was only detected in 3 of 23 samples in the nontidal part of the creek. 1,1,2,2-Tetrachloroethane was detected in 43 percent of the tidal samples (26 of 61 samples), but was detected at only two nontidal sites and only during November 1999. Three samples were collected from the tidal Gunpowder River about 300 feet from the mouth of Canal Creek in May 2000, and none of the samples contained volatile organic compound concentrations above detection levels. Volatile organic compound concentrations in surface water were highest in the reaches of the creek adjacent to the areas with the highest known levels of ground-water contamination. The load of total volatile organic compounds from Canal Creek to the Gunpowder River is approximately 1.85 pounds per day (0

  13. Ground-water and surface-water quality data for the West Branch Canal Creek area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Spencer, Tracey A.; Phelan, Daniel J.; Olsen, Lisa D.; Lorah, Michelle M.

    2001-01-01

    This report presents ground-water and surface-water quality data from samples collected by the U.S. Geological Survey from November 1999 through May 2001 at West Branch Canal Creek, Aberdeen Proving Ground, Maryland. The report also provides a description of the sampling and analytical methods that were used to collect and analyze the samples, and includes an evaluation of the quality-assurance data. The ground-water sampling network included two 4-inch wells, two 2-inch wells, sixteen 1-inch piezometers, one hundred thirteen 0.75-inch piezometers, two 0.25-inch flexible-tubing piezo-meters, twenty-seven 0.25-inch piezometers, and forty-two multi-level monitoring system depths at six sites. Ground-water profiler samples were collected from nine sites at 34 depths. In addition, passive-diffusion-bag samplers were deployed at four sites, and porous-membrane sampling devices were installed in the upper sediment at five sites. Surface-water samples were collected from 20 sites. Samples were collected from wells and 0.75-inch piezometers for measurement of field parameters and reduction-oxidation constituents, and analysis of inorganic and organic constituents, during three sampling events in March?April and June?August 2000, and May 2001. Surface-water samples were collected from November 1999 through September 2000 during five sampling events for analysis of organic constituents. Ground-water profiler samples were collected in April?May 2000, and analyzed for field measure-ments, reduction-oxidation constituents, and inorganic constituents and organic constituents. Passive-diffusion-bag samplers were installed in September 2000, and samples were analyzed for organic constituents. Multi-level monitoring system samples were collected and analyzed for field measurements and reduction-oxidation con-stituents, inorganic constituents, and organic con-stituents in March?April and June?August 2000. Field measurements and organic constituents were collected from 0.25-inch

  14. Simulation of ground-water flow and transport of chlorinated hydrocarbons at Graces Quarters, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Tenbus, Frederick J.; Fleck, William B.

    2001-01-01

    Military activity at Graces Quarters, a former open-air chemical-agent facility at Aberdeen Proving Ground, Maryland, has resulted in ground-water contamination by chlorinated hydrocarbons. As part of a ground-water remediation feasibility study, a three-dimensional model was constructed to simulate transport of four chlorinated hydrocarbons (1,1,2,2-tetrachloroethane, trichloroethene, carbon tetrachloride, and chloroform) that are components of a contaminant plume in the surficial and middle aquifers underlying the east-central part of Graces Quarters. The model was calibrated to steady-state hydraulic head at 58 observation wells and to the concentration of 1,1,2,2-tetrachloroethane in 58 observation wells and 101direct-push probe samples from the mid-1990s. Simulations using the same basic model with minor adjustments were then run for each of the other plume constituents. The error statistics between the simulated and measured concentrations of each of the constituents compared favorably to the error statisticst,1,2,2-tetrachloroethane calibration. Model simulations were used in conjunction with contaminant concentration data to examine the sources and degradation of the plume constituents. It was determined from this that mixed contaminant sources with no ambient degradation was the best approach for simulating multi-species solute transport at the site. Forward simulations were run to show potential solute transport 30 years and 100 years into the future with and without source removal. Although forward simulations are subject to uncertainty, they can be useful for illustrating various aspects of the conceptual model and its implementation. The forward simulation with no source removal indicates that contaminants would spread throughout various parts of the surficial and middle aquifers, with the100-year simulation showing potential discharge areas in either the marshes at the end of the Graces Quarters peninsula or just offshore in the estuaries. The

  15. Inorganic and organic ground-water chemistry in the Canal Creek area of Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Lorah, M.M.; Vroblesky, D.A.

    1989-01-01

    Groundwater chemical data were collected from November 1986 through April 1987 in the first phase of a 5-year study to assess the possibility of groundwater contamination in the Canal Creek area of Aberdeen Proving Ground, Maryland. Water samples were collected from 87 observation wells screened in Coastal Plain sediments; 59 samples were collected from the Canal Creek aquifer, 18 from the overlying surficial aquifer, and 10 from the lower confined aquifer. Dissolved solids, chloride, iron, manganese, fluoride, mercury, and chromium are present in concentrations that exceed the Federal maximum contaminant levels for drinking water. Elevated chloride and dissolved-solids concentrations appear to be related from contaminant plumes but also could result from brackish-water intrusion. Excessive concentrations of iron and manganese were the most extensive water quality problems found among the inorganic constituents and are derived from natural dissolution of minerals and oxide coatings in the aquifer sediments. Volatile organic compounds are present in the Canal Creek and surficial aquifers, but samples from the lower confined aquifer do not show any evidence of contamination by inorganic or organic chemicals. The volatile organic contaminants detected in the groundwater and their maximum concentrations (in micrograms/L) include 1,1,2,2- tetrachloroethane (9,000); carbon tetrachloride (480); chloroform (460); 1,1,2-trichloroethane (80); 1,2-dichloroethane (990); 1,1-dichloroethane (3.1); tetrachloroethylene (100); trichloroethylene (1,800); 1,2-trans- dichloroethylene (1,200); 1,1-dichloroethylene (4.4); vinyl chloride (140); benzene (70); and chlorobenzene (39). On the basis of information on past activities in the study area, some sources of the volatile organic compounds include: (1) decontaminants and degreasers; (2) clothing-impregnating operations; (3) the manufacture of impregnite material; (4) the manufacture of tear gas; and (5) fuels used in garages and at

  16. Creating artificial reefs from decommissioned platforms in the North Sea: review of knowledge and proposed programme of research

    Energy Technology Data Exchange (ETDEWEB)

    Aabel, J.P.; Cripps, S.J.; Jensen, A.C.; Picken, G.

    1997-12-31

    This report relates to the case for research and development work on North Sea artificial reefs. There are potentially many benefits that can be derived from platform reefs, for example as an aid to increased fishing yield for commercial fishermen, a means of enhancing fish stocks and protecting habitat for physical damage. In addition there may be a reduction in decommissioning costs for the oil industry and in negative environmental impacts inherent with land-based decommissioning techniques. Negative impacts could be loss of fishing area and changes in the ecosystem. The report will be focused towards practically applicable results that will aid the decision making process. 129 refs., 13 figs., 18 tabs.

  17. Legal aspects of shut-down and decommissioning of nuclear power plants; Rechtsfragen der Stilllegung und des Rueckbaus von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Leidinger, Tobias [Luther Rechtsanwaltsgesellschaft, Duesseldorf (Germany)

    2016-10-15

    The legally phase-out the peaceful use of nuclear energy in Germany has put into focus the topics decommissioning and dismantling of nuclear power plants. Technically and legally issues have to be managed, which are often closely connected. From a legal perspective it is important, that the initial situation of operation and operation phases of the nuclear power plant are settled. Some of the most relevant legal issues are more accurate presented and discussed. They are related to the period after shut-down and before granting the decommissioning license.

  18. An analytical approach to γ-ray self-shielding effects for radioactive bodies encountered nuclear decommissioning scenarios.

    Science.gov (United States)

    Gamage, K A A; Joyce, M J

    2011-10-01

    A novel analytical approach is described that accounts for self-shielding of γ radiation in decommissioning scenarios. The approach is developed with plutonium-239, cobalt-60 and caesium-137 as examples; stainless steel and concrete have been chosen as the media for cobalt-60 and caesium-137, respectively. The analytical methods have been compared MCNPX 2.6.0 simulations. A simple, linear correction factor relates the analytical results and the simulated estimates. This has the potential to greatly simplify the estimation of self-shielding effects in decommissioning activities.

  19. Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas

    Energy Technology Data Exchange (ETDEWEB)

    Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-08-01

    This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

  20. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  1. Progress report on decommissioning activities at the Fernald Environmental Management Project (FEMP) site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The Fernald Environmental Management Project (FEMP), is located about 18 miles northwest of Cincinnati, Ohio. Between 1953 and 1989, the facility, then called the Feed Material Production Center or FMPC, produced uranium metal products used in the eventual production of weapons grade material for use by other US Department of Energy (DOE) sites. In 1989, FMPC`s production was suspended by the federal government in order to focus resources on environmental restoration versus defense production. In 1992, Fluor Daniel Fernald assumed responsibility for managing all cleanup activities at the FEMP under contract to the DOE. In 1990, as part of the remediation effort, the site was divided into five operable units based on physical proximity of contaminated areas, similar amounts of types of contamination, or the potential for a similar technology to be used in cleanup activities. This report continues the outline of the decontamination and decommissioning (D and D) activities at the FEMP site Operable Unit 3 (OU3) and provides an update on the status of the decommissioning activities. OU3, the Facilities Closure and Demolition Project, involves the remediation of more than 200 uranium processing facilities. The mission of the project is to remove nuclear materials stored in these buildings, then perform the clean out of the buildings and equipment, and decontaminate and dismantle the facilities.

  2. Summary of comments received from workshops on radiological criteria for decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C. [Advanced Systems Technology, Inc., Atlanta, GA (United States)

    1994-01-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for site cleanup and decommissioning of NRC-licensed facilities. Open public meetings were held during 1993 in Chicago, IL, San Francisco, CA, Boston, MA, Dallas, TX, Philadelphia, PA, Atlanta, GA, and Washington, DC. Interested parties were invited to provide input on the rulemaking issues before the NRC staff develops a draft proposed rule. This report summarizes 3,635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed letters from individuals and organizations. No analysis or response to the comments is included. The comments reflect a broad spectrum of viewpoints on the issues related to radiological criteria for site cleanup and decommissioning. The NRC also held public meetings on the scope of the Generic Environmental Impact Statement (GEIS) during July 1993. The GEIS meetings were held in Washington, DC., San Francisco, CA, Oklahoma City, OK, and Cleveland, OH. Related comments from these meetings were reviewed and comments which differed substantially from those from the workshops are also summarized in the body of the report. A summary of the comments from the GEIS scoping meetings is included as an Appendix.

  3. The Optimization of Radioactive Waste Management in the Nuclear Installation Decommissioning Process

    Energy Technology Data Exchange (ETDEWEB)

    Zachar, Matej; Necas, Vladimir [Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia)

    2008-07-01

    The paper presents a basic characterization of nuclear installation decommissioning process especially in the term of radioactive materials management. A large amount of solid materials and secondary waste created after implementation of decommissioning activities have to be managed considering their physical, chemical, toxic and radiological characteristics. Radioactive materials should be, after fulfilling all the conditions defined by the authorities, released to the environment for the further use. Non-releasable materials are considered to be a radioactive waste. Their management includes various procedures starting with pre-treatment activities, continuing with storage, treatment and conditioning procedures. Finally, they are disposed in the near surface or deep geological repositories. Considering the advantages and disadvantages of all possible ways of releasing the material from nuclear installation area, optimization of the material management process should be done. Emphasis is placed on the radiological parameters of materials, availability of waste management technologies, waste repositories and on the radiological limits and conditions for materials release or waste disposal. Appropriate optimization of material flow should lead to the significant savings of money, disposal capacities or raw material resources. Using a suitable calculation code e.g. OMEGA, the evaluation of the various material management scenarios and selection of the best one, based on the multi-criterion analysis, should be done. (authors)

  4. Comments received on proposed rule on radiological criteria for decommissioning and related documents

    Energy Technology Data Exchange (ETDEWEB)

    Page, G.; Caplin, J.; Smith, D. [and others

    1996-03-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As a part of this action, the Commission published in the Federal Register (59 FR 43200), on August 22, 1994, a proposed rule on radiological criteria for decommissioning, soliciting comments both on the rule as proposed and on certain specific items as identified in its supplementary statement of considerations. A draft Generic Environmental Impact Statement (GEIS) in support of the rule, also published in August 1994 as NUREG-1496, along with its Appendix A (NUREG-1501), were also made available for comment. A staff working draft on regulatory guidance (NUREG-1500)was also made available. This report summarizes the 1,309 comments on the proposed rule and supplementary items and the 311 comments on the GEIS as excerpted from 101 docketed letters received associated in the Federal/Register notice. Comments from two NRC/Agreement-States meetings are also summarized.

  5. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

  6. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  7. Study on Evaluation of Project Management Data for Decommissioning of Uranium Refining and Conversion Plant - 12234

    Energy Technology Data Exchange (ETDEWEB)

    Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); Shibahara, Yuji [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); University of Fukui, Fukui-shi, Fukui, 910-8507 (Japan); Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Tanaka, Yoshio; Sugitsue, Noritake [Japan Atomic Energy Agency, Kagamino-cho, Tomata-gun, Okayama, 708-0698 (Japan)

    2012-07-01

    Some of nuclear facilities that would no longer be required have been decommissioned in JAEA (Japan Atomic Energy Agency). A lot of nuclear facilities have to be decommissioned in JAEA in near future. To implement decommissioning of nuclear facilities, it was important to make a rational decommissioning plan. Therefore, project management data evaluation system for dismantling activities (PRODIA code) has been developed, and will be useful for making a detailed decommissioning plan for an object facility. Dismantling of dry conversion facility in the uranium refining and conversion plant (URCP) at Ningyo-toge began in 2008. During dismantling activities, project management data such as manpower and amount of waste generation have been collected. Such collected project management data has been evaluated and used to establish a calculation formula to calculate manpower for dismantling equipment of chemical process and calculate manpower for using a green house (GH) which was a temporary structure for preventing the spread of contaminants during dismantling. In the calculation formula to calculate project management data related to dismantling of equipment, the relation of dismantling manpower to each piece of equipment was evaluated. Furthermore, the relation of dismantling manpower to each chemical process was evaluated. The results showed promise for evaluating dismantling manpower with respect to each chemical process. In the calculation formula to calculate project management data related to use of the GH, relations of GH installation manpower and removal manpower to GH footprint were evaluated. Furthermore, the calculation formula for secondary waste generation was established. In this study, project management data related to dismantling of equipment and use of the GH were evaluated and analyzed. The project management data, manpower for dismantling of equipment, manpower for installation and removal of GH, and secondary waste generation from GH were considered

  8. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  9. Plan for fully decontaminating and decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick, Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This volume contains the following 3 attachments: (1) Plan for Fully Decontamination and Decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick; (2) Environmental Assessment for Decontamination and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA; and (3) WARD-386, Quality Assurance Program Description for Decontamination and Decommissioning Activities.

  10. 30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

    Science.gov (United States)

    2010-07-01

    ... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE OIL AND GAS AND SULPHUR OPERATIONS IN THE OUTER CONTINENTAL SHELF Pipelines and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI...

  11. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 4 - FUEL CHANNEL ASSEMBLY

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2014-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, costeffective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

  12. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 3 - FUEL CHANNEL REFERENCES

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2014-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, cost-effective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

  13. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 2 - FUEL CHANNEL PRESENTATION

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2014-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, costeffective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning.The final aim of decommissioning is to recover the geographic site to its original condition.

  14. Características da carcaça de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos terminados em confinamento

    OpenAIRE

    Perotto,Daniel; Moletta,José Luiz; Cubas,Antonio Carlos

    1999-01-01

    Foram analisadas quatorze características quantitativas das carcaças de 137 machos bovinos inteiros pertencentes aos grupos Canchim (Ca), Aberdeen Angus (Ab), 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab e 5/8Ab+3/8Ca, nascidos na Estação Experimental Fazenda Modelo, em Ponta Grossa-PR, no período de 1988 a 1993. As médias para a idade e para o peso ao início do confinamento, duração do confinamento, idade e peso ao abate foram, respectivamente, 737 dias, 356kg, 97 dias, 834 dias e 468kg. Durante o ...

  15. Focused feasibility study for surface soil at the main pits and pushout area, J-field toxic burning pits area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Patton, T.; Benioff, P.; Biang, C.; Butler, J. [and others

    1996-06-01

    The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). J-Field is located within the Edgewood Area of APG in Harford County, Maryland. Since World War II, activities in the Edgewood Area have included the development, manufacture, testing, and destruction of chemical agents and munitions. These materials were destroyed at J-Field by open burning/open detonation. Portions of J-Field continue to be used for the detonation and disposal of unexploded ordnance (UXO) by open burning/open detonation under authority of the Resource Conservation and Recovery Act.

  16. Preliminary assessment of microbial communities and biodegradation of chlorinated volatile organic compounds in wetlands at Cluster 13, Lauderick Creek area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Lorah, Michelle M.; Voytek, Mary A.; Spencer, Tracey A.

    2003-01-01

    A preliminary assessment of the microbial communities and biodegradation processes for chlorinated volatile organic compounds was con-ducted by the U.S. Geological Survey in wetlands at the Cluster 13, Lauderick Creek area at Aberdeen Proving Ground, Maryland. The U.S. Geological Survey collected wetland sediment samples from 11 sites in the Lauderick Creek area for microbial analyses, and used existing data to evaluate biodegradation processes and rates. The bacterial and methanogen communities in the Lauderick Creek wetland sediments were similar to those observed in a previous U.S. Geological Survey study at the West Branch Canal Creek wet-land area, Aberdeen Proving Ground. Evaluation of the degradation rate of 1,1,2,2-tetrachloroethane and the daughter compounds produced also showed similar results for the two wetlands. How-ever, a vertical profile of contaminant concentra-tions in the wetlands was available at only one site in the Lauderick Creek area, and flow velocities in the wetland sediment are unknown. To better evaluate natural attenuation processes and rates in the wetland sediments at Lauderick Creek, chemi-cal and hydrologic measurements are needed along ground-water flowpaths in the wetland at additional sites and during different seasons. Nat-ural attenuation in the wetlands, enhanced biore-mediation, and constructed wetlands could be feasible remediation methods for the chlorinated volatile organic compounds discharging in the Lauderick Creek area. The similarities in the microbial communities and biodegradation pro-cesses at the Lauderick Creek and West Branch Canal Creek areas indicate that enhanced bioreme-diation techniques currently being developed for the West Branch Canal Creek wetland area would be transferable to this area.

  17. Can Decommissioned Oil Pads in Boreal Alberta BE Reclaimed to Carbon Accumulating Peatlands?

    Science.gov (United States)

    Wieder, R.; Vitt, D. H.; Mowbray, S.

    2010-12-01

    In northern Alberta where peatland ecosystems are a dominant landscape feature, construction of oil drilling pads and access roads is a major disturbance. Reclamation of decommissioned oil pads has been hampered by the lack of research. At two decommissioned oil pads at Shell Oil’s Peace River Complex (northeastern Alberta), initially constructed in a bog/fen complex, we established a field experiment to assess reclamation approaches that could lead to a system reflecting undisturbed peatland structure (vegetation composition) and function (net carbon accumulation). In the fall of 2007, mineral soil was removed from two decommissioned pads in areas approximately 100-m x 30-m creating a mineral surface at or near the surrounding bog water table level. We established the following treatments: pad (fertilized vs. unfertilized); water table position (at and 5-cm above the surrounding bog water level); texture (tilling soil amendments into the mineral soil or not); amendment (controls; commercial peat, peat that had been stockpiled in a farmer’s field; landscape fabric; slough hay (native species hay from harvested from local farms), aspen wood chips); planting (in 1-m x 1-m subplots within 2-m x 2-m amendment plots: no planting, 9 Carex aquatilis plants, 5 C. aquatilis and 4 Salix lutea plants; 3 C. aquatilis, 3 S. lutea and 3 Larix laricina seedlings). Treatments were nested (planting within amendment, within texture, within water table level, within pad), with 6 replicate 2-m x 2-m plots of each amendment within each pad x texture x water level combination. Net CO2 exchange was quantified under a range of PAR conditions from full sunlight to complete darkness in each 1-m x 1-m planting subplot repeatedly during the summers of 2008, 2009 and 2010 using closed chambers and infrared gas analyzers. Both dark respiration and maximum net ecosystem production (NEPSAT; net CO2 sequestration when PAR>1000 μmol m-2 s-1) exhibited year x planting interactions (p<0.0001 and

  18. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

  19. Proceedings of the twenty-third annual British Columbia mine reclamation symposium: mine decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    The symposium covered a spectrum of reclamation issues relevant to mining in British Columbia. The proceedings contain the twenty-one technical papers presented and a report by the awards subcommittee concerning citations awarded. Papers are included on native species in reclamation, bat conservation, biological removal of selenium, wetland cells for removing heavy metals leachates, end land use plan for a copper mine, environmental projects at Fording Coal, reclamation at a nickel plate tailings facility, forestry for end use, contaminated site legislation, compliance, environmental management considerations, acid rock drainage prediction, granular cover system for tailings management, long-term management of tailings and tailings dams at decommissioned mining properties, mine subsidence risk management, reclaiming subsidence in abandoned mining areas, and reclamation of mine openings. Two papers are abstracted separately.

  20. Investigation of induced radioactivity in the CERN Large Electron Positron collider for its decommissioning

    CERN Document Server

    Silari, Marco

    2004-01-01

    The future installation of the Large Hadron Collider in the tunnel formerly housing the Large Electron Positron collider (LEP) required the dismantling of the latter after 11-year operation. As required by the French legislation, an extensive theoretical study was conducted before decommissioning to establish the possible activation paths both in the accelerator and in the four experiments (L3, ALEPH, OPAL and DELPHI) installed around the ring. The aim was to define which areas may contain activated material and which ones would be completely free of activation. The four major sources of activation in LEP, i.e., distributed and localized beam losses, synchrotron radiation and the super-conducting RF cavities, were investigated. Conversion coefficients from unit lost beam power to induced specific activity were established for a number of materials. A similar study was conducted for the four experiments, evaluating the four potential sources of induced radioactivity, namely e**+e **- annihilation events, two-p...

  1. Assessment of the radiological impact of a decommissioning nuclear power plant in Italy

    CERN Document Server

    Petraglia, A; De Cesare, M; De Cesare, N; Quinto, F; Terrasi, F; D'Onofrio, A; Steier, P; Fifield, L K; Esposito, A M; 10.1051/radiopro/2012010

    2012-01-01

    The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

  2. Radiological survey support activities for the decommissioning of the Ames Laboratory Research Reactor Facility, Ames, Iowa

    Energy Technology Data Exchange (ETDEWEB)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1984-09-01

    At the request of the Engineering Support Division of the US Department of Energy-Chicago Operations Office and in accordance with the programmatic overview/certification responsibilities of the Department of Energy Environmental and Safety Engineering Division, the Argonne National Laboratory Radiological Survey Group conducted a series of radiological measurements and tests at the Ames Laboratory Research Reactor located in Ames, Iowa. These measurements and tests were conducted during 1980 and 1981 while the reactor building was being decontaminated and decommissioned for the purpose of returning the building to general use. The results of these evaluations are included in this report. Although the surface contamination within the reactor building could presumably be reduced to negligible levels, the potential for airborne contamination from tritiated water vapor remains. This vapor emmanates from contamination within the concrete of the building and should be monitored until such time as it is reduced to background levels. 2 references, 8 figures, 6 tables.

  3. A DECONTAMINATION PROCESS FOR METAL SCRAPS FROM THE DECOMMISSIONING OF TRR

    Energy Technology Data Exchange (ETDEWEB)

    Wei, T.Y.; Gan, J.S.; Lin, K.M.; Chung, Z.J.

    2003-02-27

    A decontamination facility including surface condition categorizing, blasting, chemical/electrochemical cleaning, very low radioactivity measuring, and melting, is being established at INER. The facility will go into operation by the end of 2004. The main purpose is to clean the dismantled metal wastes from the decommissioning of Taiwan Research Reactor (TRR). The pilot test shows that over 70% of low level metal waste can be decontaminated to very low activity and can be categorized as BRC (below regulatory concern) waste. All the chemical decontamination technologies applied are developed by INER. In order to reduce the secondary wastes, chemical reagents will be regenerated several times with a selective precipitation method. The exhausted chemical reagent will be solidified with INER's patented process. The total secondary waste is estimated about 0.1-0.3 wt.% of the original waste. This decontamination process is accessed to be economic and feasible.

  4. Review Of Decommissioning Experience In Spent Fuel Reprocessing Facilities at Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Guiberteau, Ph.; Vendroux, M. [CODEM GIE, BP 21004, 30201 Bagnols sur Ceze cedex (France); Berlan, C. [COGEMA Reprocessing Business Unit, 2, rue Paul Dautier - BP.4, 78141 Velizy Cedex (France)

    2003-07-01

    Final shutdown and decontamination, dismantling, and legacy waste retrieval programs are currently in progress at the Marcoule nuclear fuel reprocessing plant in southern France. They began in 1998 and will continue until about 2040. CODEM is the funding, decision-making and inspection organization for these decommissioning operations, COGEMA is the nuclear operator and the industrial contractor. After an overview of the facilities, the project and the participants, most significant operations are discussed in greater detail. High activity levels and the presence of large quantities of {alpha}-emitters complicate operating and waste treatment conditions. The major issues impacting cost-effectiveness-scenario, waste removal and project organization will be highlighted in the conclusion.

  5. Decontamination and decommissioning plan for processing contaminated NaK at the INEL

    Energy Technology Data Exchange (ETDEWEB)

    LaRue, D.M.; Dolenc, M.R.

    1986-09-01

    This decontamination and decommissioning (D&D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D&D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

  6. Decontamination and decommissioning plan for processing contaminated NaK at the INEL

    Energy Technology Data Exchange (ETDEWEB)

    LaRue, D.M.; Dolenc, M.R.

    1986-09-01

    This decontamination and decommissioning (D D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

  7. Decontamination and decommissioning project of the TRIGA Mark-2 and 3 research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jung, K. J.; Baik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, B. J.; Kim, J. K.; Yang, S. H

    2000-01-01

    During the review on the decommissioning plan and environmental impact assessment report by the KINS, the number of the inquired items were two hundred and fifty one, and the answers were made and sent until September 10, 1999, as the screened review results were reported to Ministry of Science and Technology(MOST) in December 14, 1999, all the reviews on the licence were over. Radioactive liquid wastes of 400 tons generated during the operation of the research reactors including reactor vessels are stored in the facility of the research reactor 1 and 2. Those liquid wastes have the low-level-radioactivity which can be discharged to the surroundings, but was wholly treated to be vaporized naturally by means of the increased numbers of the natural vaporization disposal facilities with the annual capacity of 200 tons for the purpose of the minimized environmental contamination.

  8. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

  9. Disposal of Steam Generators from Decommissioning of PWR Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Walberg, Mirko; Viermann, Joerg; Beverungen, Martin [GNS Gesellschaft fuer Nuklear-Service mbH, Hollestrasse 7A, 45127 Essen (Germany); Kemp, Lutz [Kernkraftwerk Stade GmbH and Co.oHG, Bassenflether Chaussee, 21683 Stade (Germany); Lindstroem, Anders [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden)

    2008-07-01

    Amongst other materials remarkable amounts of radioactively contaminated or activated scrap are generated from the dismantling of Nuclear Power Plants. These scrap materials include contaminated pipework, fittings, pumps, the reactor pressure vessel and other large components, most of them are heat exchangers. Taking into account all commercial and technical aspects an external processing and subsequent recycling of the material might be an advantageous option for many of these components. The disposal of steam generators makes up an especially challenging task because of their measures, their weight and compared to other heat exchangers high radioactive inventory. Based on its experiences from many years of disposal of smaller components of NPP still in operation or under decommissioning GNS and Studsvik Nuclear developed a concept for disposal of steam generators, also involving experiences made in Sweden. The concept comprises transport preparations and necessary supporting documents, the complete logistics chain, steam generator treatment and the processing of arising residues and materials not suitable for recycling. The first components to be prepared, shipped and treated according to this concept were four steam generators from the decommissioning of the German NPP Stade which were removed from the plant and shipped to the processing facility during the third quarter of 2007. Although the plant had undergone a full system decontamination, due to the remaining contamination in a number of plugged tubes the steam generators had to be qualified as industrial packages, type 2 (IP-2 packages), and according to a special requirement of the German Federal Office for Radiation Protection a license for a shipment under special arrangement had to be applied for. The presentation gives an overview of the calculations and evidences required within the course of the IP-2 qualification, additional requirements of the competent authorities during the licensing procedure as

  10. Long-lived radionuclides in residues from operation and decommissioning of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lopez-Gutierrez, J.M., E-mail: lguti@us.es [Centro Nacional de Aceleradores (CNA), c/Thomas Alva Edison n Degree-Sign 7, 41092 Sevilla (Spain); University of Sevilla, Departamento de Fisica Aplicada I, c/Virgen de Africa, n Degree-Sign 7, 41011 Sevilla (Spain); Gomez-Guzman, J.M.; Chamizo, E.; Peruchena, J.I. [Centro Nacional de Aceleradores (CNA), c/Thomas Alva Edison n Degree-Sign 7, 41092 Sevilla (Spain); Garcia-Leon, M. [University of Sevilla, Departamento de Fisica Atomica, Molecular y Nuclear, Apdo. 1065, 41080 Sevilla (Spain)

    2013-01-15

    Radioactive residues, in order to be classified as Low-Level Waste (LLW), need to fulfil certain conditions; the limitation of the maximum activity from long-lived radionuclides is one of these requirements. In order to verify compliance to this limitation, the abundance of these radionuclides in the residue must be determined. However, performing this determination through radiometric methods constitutes a laborious task. In this work, {sup 129}I concentrations, {sup 239+240}Pu activities, and {sup 240}Pu/{sup 239}Pu ratios are determined in low-level radioactive residues, including resins and dry sludge, from nuclear power plants in Spain. The use of Accelerator Mass Spectrometry (AMS) enables high sensitivities to be achieved, and hence these magnitudes can be re determined with good precision. Results present a high dispersion between the {sup 129}I and {sup 239+240}Pu activities found in various aliquots of the same sample, which suggests the existence of a mixture of resins with a variety of histories in the same container. As a conclusion, it is shown that activities and isotopic ratios can provide information on the processes that occur in power plants throughout the history of the residues. Furthermore, wipes from the monitoring of surface contamination of the Jose Cabrera decommissioning process have been analyzed for {sup 129}I determination. The wide range of measured activities indicates an effective dispersal of {sup 129}I throughout the various locations within a nuclear power plant. Not only could these measurements be employed in the contamination monitoring of the decommissioning process, but also in the modelling of the presence of other iodine isotopes.

  11. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  12. Fixed-Price Subcontracting for Decontamination and Decommissioning of Small Facilities at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Harper, M. A.; Julius, J. F. K.; McKenna, M. K.

    2002-02-26

    Abandoned facilities were decontaminated and decommissioned in preparation for final remediation of Solid Waste Storage Area (SWSA) 4 at Oak Ridge National Laboratory. The facilities varied in age from approximately 5 years to more than 40 years, with radiological conditions ranging from clean to highly contaminated with fission products. A fixed-price subcontract (FPSC) was awarded by the U.S. Department of Energy's (DOE's) Environmental Management (EM) Management and Integration (M&I) contractor for decontamination and decommissioning (D&D) of these facilities. Included in the FPSC scope were the following: preparation of pre-D&D regulatory documentation; demolition of surface structures to slab; stabilization of below-grade structures; waste management and disposal; and preparation of post-D&D regulatory documentation. Using stand-off techniques to the extent possible, building structures and ancillary equipment were prepared for demolition and demolished. A fixative coating system was used in conjunction with continuous water misting to control airborne contamination. Demolition waste consisted of two major streams: clean construction and demolition waste and low-level (radioactive) waste. The debris was size-reduced and packaged, again via remote means. At all times during the D&D, personnel safety, environmental compliance, and as low as reasonably achievable exposure considerations were paramount. Upon completion of D&D activities, each site was inspected and accepted by the M&I contractor. This project is a success story for fixed-price subcontracting of D&D work under DOE's M&I arrangement.

  13. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

  14. Evaluation on radioactive waste for the decommissioning of deuterium critical assembly (DCA)

    Energy Technology Data Exchange (ETDEWEB)

    Konno, S.; Fukuda, S.; Hazama, T.; Endou, K.; Hashimoto, M. [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Yoshizawa, S. [Kawasaki Heavy Industries, Ltd., Tokyo (Japan)

    2002-10-01

    Deuterium Critical Assembly (DCA) is a critical facility with 1 kW maximum thermal output reached its initial criticality in 1969. DCA operations were stopped on 26th September 2001, then it has been planed to submit a legal application for decommissioning of DCA to MEXT and to shift to decommissioning phase. In this work, we have evaluated the calculation value of neutron flux by comparison with an actual measurement in biological shield and the amount of contaminated radioactive materials etc. to make a document on estimation of the inventories and the wastes quantity etc. in the legal application. Results are as follows. 1. Fast, epithermal and thermal neutron flux calculated have exceeded the measurement data at almost all location. Therefore concentration of activated materials calculated by neutron flux calculation value is estimated higher than actual that. 2. The amount of radioactive materials that contaminated by nuclides other than tritium is estimated about 3.0 x 10{sup 7}Bq. The concentration of tritium-contaminated radioactive materials is estimated about 4.1 x 10{sup 1}Bq/g at the maximum in concrete, about 7.6 x 10{sup -2}Bq/g in the surface of aluminum plumbing. 3. Consequential waste quantity (solid waste) to radioactive waste generated in total process of dismantling is estimated about 30ton. As for Radioactive liquid waste quantity, moderator for specimen is estimated about 1.4m{sup 3}, consequential liquid wastes is estimated about 300m{sup 3}. 4. The amount of Tritium generated in dismantling (radioactive gas waste) is estimated about 7.25 x 10{sup 8}Bq in dismantling of heavy water system facility, measurement control system facility and neutron reactor. (author)

  15. Estimating boiling water reactor decommissioning costs. A user`s manual for the BWR Cost Estimating Computer Program (CECP) software: Draft report for comment

    Energy Technology Data Exchange (ETDEWEB)

    Bierschbach, M.C. [Pacific Northwest Lab., Richland, WA (United States)

    1994-12-01

    With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the U.S. Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personal computer, provides estimates for the cost of decommissioning BWR power stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.

  16. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - main report. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2), which is a boiling water reactor (BWR), located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low- level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  17. Decommissioning Programme Management: reducing risk and cost while accelerating schedules through improved planning, Earned Value Management and safe work execution

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, S.E. [CH2M Hill International Nuclear Services (United States)

    2008-07-01

    CH2M HILL experience includes more than two decades of managing nuclear facilities and providing clean-up and operations support for commercial and government facilities worldwide. Our expertise ranges from decommissioning and defence sector businesses to nuclear technology development and innovation. Our approach places top priority on the safe execution of work while reducing both risk and cost. Our nuclear services include: programme management, nuclear safety analysis, radiological protection, radioactive waste management, nuclear remediation, nuclear materials and waste transportation management, nuclear safeguards and security services, and nuclear decontamination and decommissioning. This paper will discuss our approach which has resulted in a strong track record of accelerating schedules and reducing costs of major nuclear programmes, including Rocky Flats, Idaho, and our work at UKAEA sites. (author)

  18. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Reilkoff, T. E.; Hetland, M. D.; O' Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  19. Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.

  20. Evaluate the radioactivity along the central thimble hole of a decommissioned heavy water research reactor using TLD approach.

    Science.gov (United States)

    Lee, Lun-Hui; Sher, Hai-Feng; Lu, I-Hsin; Pan, Lung-Kwang

    2012-04-01

    The radioactivity along the central thimble hole of a decommissioned heavy water research reactor, TRR, was evaluated using TLD approach. The decay radionuclide was verified to be Co-60. The dose along the TRR central thimble hole was detected and revised by performing an unfolding analysis. The revised data reduced to 70-90% of the original data (for example, the maximum dose rate was reduced from 6447 to 4831 mSv/h,) and were more reliable.

  1. VGH Mannheim: legitimacy of the decommissioning license for a nuclear power plant; VGH Mannheim: Rechtmaessigkeit der Stilllegungsgenehmigung fuer ein Kernkraftwerk

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2015-03-16

    The contribution describes the details of the court (VGH) decision on the legitimacy of the decommissioning license for the NPP Obrigheim. Inhabitants of the neighborhood (3 to 4.5 km distance from the NPP) are suspect hazards for life, health and property due to the dismantling of the nuclear power plant in case of an accident during the licensed measures or a terroristic attack with radioactive matter release.

  2. Very low level waste disposal in France. A key tool for the management for decommissioning wastes in France

    Energy Technology Data Exchange (ETDEWEB)

    Duetzer, Michel [Andra - Agence Nationale pour la Gestion des Dechets Radioactives, Chatenay-Malabry (France). Direction Industrielle

    2015-07-01

    At the end of the 90{sup th}, France had to deal with the emerging issue of the management of wastes resulting from decommissioning operations of nuclear facilities. A specific regulation was issued and Andra, the French National Radioactive Waste Management Agency, developed a dedicated near surface disposal facility to accommodate very low level radioactive wastes. After more than 10 years of operation, this facility demonstrated it can provide efficient and flexible solutions for the management of decomissioning wastes.

  3. Decommissioning of nuclear power plants in the US - a travel report; Avveckling av kaernkraftverk i USA - en reserapport

    Energy Technology Data Exchange (ETDEWEB)

    Efraimsson, H.; Lindhe, J.C.; Malmqvist, L.; Lund, I.; Welleman, E

    1999-03-01

    This report summarises information and impressions from a journey in north-east USA. The purpose of the journey was to study the on-going decommissioning of nuclear power plants - mainly how it is regulated by the competent authorities, but also how it is performed in practice. The journey included visits at the US Nuclear Regulatory Commission, the company Duke Engineering and Services, and the two nuclear power plants Haddam Neck and Maine Yankee

  4. Decommissioning of the ASTRA research reactor: Dismantling the auxiliary systems and clearance and reuse of the buildings

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2008-01-01

    Full Text Available The paper presents work performed in the last phase of the decommissioning of the ASTRA research reactor at the Austrian Research Centers Seibersdorf. Dismantling the pump room installations and the ventilation system, as well as the clearance of the buildings is described. Some conclusions and summary data regarding the timetable, material management, and the cost of the entire project are also presented.

  5. The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

    Energy Technology Data Exchange (ETDEWEB)

    Zeleznik, Nadja; Kralj, Metka [ARAO, Parmova 53, 1000 Ljubljana (Slovenia); Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea [APO, Savska 41, Zagreb (Croatia); Mele, Irena [IAEA, Vienna (Austria)

    2010-07-01

    The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

  6. General framework and basis of decommissioning of nuclear facilities; Marco general y bases de los desmantelamientos de las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, J. L.; Martin, N.; Correa, C.

    2013-07-01

    This article summarizes the legal framework defining the strategies, the main activities and the basic responsibilities and roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the most relevant projects and activities already developed and/or ongoing nowadays, which have positioned Spain within the small group of countries having an integrated and proved experience and know how in this particular field. (Author)

  7. Selection of optimal treatment procedures for non-standard radioactive waste arising from decommissioning of NPP after accident

    Energy Technology Data Exchange (ETDEWEB)

    Strážovec, Roman, E-mail: strazovec.roman@javys.sk [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); JAVYS, a.s., Tomášikova 22, 821 02 Bratislava (Slovakia); Hrnčíř, Tomáš [DECOM, a.s., Sibírska 1, 917 01 Trnava (Slovakia); Lištjak, Martin [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); VUJE, a.s., Okružná 5, 918 64 Trnava (Slovakia); Nečas, Vladimír [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia)

    2016-05-15

    The decommissioning of nuclear power plants is becoming a standard industrial activity where the optimization processes of partial activities are inevitable mainly for technical and economic reasons. In Slovakia, the decommissioning of A1 NPP is very specific case because A1 NPP is rare type of NPP (prototype) and furthermore its operation was affected by the accident. A large number of specific non-standard radioactive waste, such as long-time storage cases (hereinafter LSC), that is not usually present within the decommissioning projects of NPP with a regular termination of operation, represent one of the significant consequences of the accident and issues arisen from follow-up activities. The presented article describes the proposal of processing and conditioning of non-standard radioactive waste (such as LSC), together with description of methodology applied in the proposal for update of waste acceptance criteria for the processing and conditioning of radioactive waste (hereinafter RAW) within Bohunice Radioactive waste Treatment and Conditioning Centre (hereinafter RWTC). The results of performed detailed analysis are summarized into new waste acceptance criteria for technological lines keeping in mind safety principles and requirements for protection of operating personnel, the public and the environment.

  8. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  9. De brest à Aberdeen, la croisière 48 du Glomar Challenger From Brest to Aberdee, Glomar Challenger Sails on Leg 48

    Directory of Open Access Journals (Sweden)

    L'équipe Scientifique Embarquée

    2006-11-01

    Full Text Available La croisière 48 du Glomar Challenger s'est déroulée en 1976 entre Brest et Aberdeen sur la marge septentrionale du Golfe de Gascogne et le Banc de Rockall. Les sept sites forés ont permis de comparer la structure et l'histoire géologique de deux marges de types différents, formées par rifting, l'une dans une mer épicontinentale, l'autre dans un craton. L'histoire de la subsidence a pu être établie. De nombreux hiatus ont été mis en évidence dans les séries déposées en mer profonde, dont certains sont contemporains d'événements connus sur le plateau continental. Des marnes noires riches en matière organique d'origine détritique ont été trouvées dans le golfe de Gascogne. Elles ont pu se déposer aussi bien en mer profonde que sur le plateau continental. Des mesures de paléomagnétisme, de flux de chaleur et des diagraphies ont été effectuées avec succès. Leg 48 by the Glomar Challenger took place in 1976, between Brest and Aberdeen, on the northern margin of the Bay of Biscay and the Rockall Bank. The seven drilling sites enabled a comparison ta be made of the structure and geological history of two different types of margins, both formed by rifting, one in an epicontinental sea and the other in a craton. The history of subsidence was determined. A great many gaps were revealed in the series deposited in deep water, including some that are contemporary with events known on the continental shelf. Blackshales rich in organic motter of detrital origin were found in the Bay of Biscay. They may have been deposited either in deep water or on the continental shelf. Successful paleomagnetism and heat flow measurements were made, along with well logging.

  10. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

  11. Decommissioning, radioactive waste management and nuclear public information issues in Italy

    Energy Technology Data Exchange (ETDEWEB)

    Enrico Mainardi [AIN - ENEA (Italy)

    2006-07-01

    the international level. The site is extremely stable from the geological point of view. It consists of a 10 km{sup 2} rock-salt layer 150 m thick protected by a clay layer 700 m thick. A similar solution has been adopted successfully for the WIPP (Waste Isolation Pilot Plant) in New Mexico (USA) operating from 1999. This paper outlines the main issues and considerations connected with decommissioning, radioactive waste management and site decision within the country together with more details on the quantities and quality of the Italian nuclear waste. The demonstration that decommissioning is feasible at reasonable costs and that wastes can be collected in a national repository with the highest safety levels will certainly further improve public attitude in favour of nuclear power. (author)

  12. Environmental survey near a decommissioning nuclear facility: example of tritium monitoring in the terrestrial environment of Creys-Malville - Environmental survey near a nuclear facility undergoing decommissioning: example of tritium monitoring in the terrestrial environment of Creys-Malville

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, C.; Gontier, G.; Chauveau, J.L. [EDF CIDEN, Division Environnement, 154 Avenue Thiers, 69458 Lyon (France); Pourcelot, L.; Roussel-Debet, S.; Cossonnet, P.C. [IRSN, LERCM Cadarache and LMRE Orsay (France); Jean-Baptiste, P. [LSCE, UMR 1572-CEA/CNRS/UVQS, 91198 Gif sur Yvette (France)

    2014-07-01

    As part of the regulatory environmental monitoring around its nuclear power plants (NPP) in France, EDF carries out more than 40.000 measurements of radionuclides in the environment every year. In addition, EDF performs more detailed radioecological surveys on all of its sites. The purposes of these surveys are: 1/ to control that radioactive discharge limits prescribed by the regulatory authority are respected, 2/ to monitor the environment of the NPPs to verify normal plant operation and to detect all possible failures in power station operation at an early stage and 3/ to establish if there is any increase of radionuclides of anthropogenic origin in the environment and to determine whether this build-up can be attributed to plant operations. Radioecological surveys are conducted in the environment surrounding each of EDF's NPPs. Samples are collected in surrounding ecosystems (terrestrial and aquatic) where the radioactive releases are discharged (liquid and gaseous discharges). These surveys results enable the examination of the spatial distribution and temporal variability of radionuclide activity in the environment throughout the reactors life, from the first fuel load to the decommissioning of the plant. The results from this monitoring have shown that EDF's nuclear power plants have only a minor effect on radionuclide levels in the environment. These results highlight the efficiency of EDF's efforts to minimise its impacts on the environment via an efficient waste management system and high operating standards of its plants. In particular, tritium is subject to special monitoring for more than 30 years; concentrations of free tritium and organically bound tritium in major environmental compartments are therefore well-known in the vicinity of French NPPs. At the end of a reactor's life, EDF has collected a large amount of reference data before decommissioning operations start. During these operations, EDF pursue the radioecological survey

  13. Qualidade do sêmen de touros das raças Aberdeen Angus e Brangus-Ibagé em frente à degeneração testicular experimental induzida por dexametasona Bulls semen quality of Aberdeen Angus and Brangus-Ibagé breeds after experimental testicular degeneration induced by dexamethasone

    Directory of Open Access Journals (Sweden)

    Marilise Mesquita Horn

    1999-09-01

    Full Text Available Foi administrada dexametasona para indução de degeneração testicular experimental em touros de uma raça taurina pura (Aberdeen Angus e de sua sintética derivada (Brangus-Ibagé. O objetivo deste estudo foi o de averiguar a diferença de sensibilidade na função gametogênica em frente à degeneração experimental. Para tal, foram avaliados os aspectos físicos e morfológicos do sêmen. Os dados obtidos foram analisados considerando o dia de coleta e genótipo. Os resultados revelaram que os dois grupos raciais comportaram-se semelhantemente ao longo das coletas. A despeito do número de animais empregados, o uso da degeneração testicular experimental possibilitou evidenciar que não há diferença entre as duas raças quanto à intensidade da degeneração e tempo necessário para o restabelecimento do quadro espermático normal.Testicular degeneration was induced by dexamethasone injection in bulls from a European breed Aberdeen Angus and a derived synthetic crossbreed (Brangus-Ibagé. Aiming to investigate differential sensibility on gametogenic function in these genotypes, physical and morphological semen characteristics were evaluated. The data analysed considered the day of the semen samples and the breed. Our results reveal that both breeds behave similarly during the experimental period. Even considering the number of bulls used in this experiment, the employed methodology gives no evidence of any difference between breeds, intensity of degeneration or time required to the reestablishment of normal sperm frequencies after experimental induction of testicular degeneration.

  14. A survey of commercially available manipulators, end-effectors, and delivery systems for reactor decommissioning activities

    Energy Technology Data Exchange (ETDEWEB)

    Henley, D.R. [Argonne National Lab., IL (United States); Litka, T.J. [Advanced Consulting Group, Chicago, IL (United States)

    1996-05-01

    Numerous nuclear facilities owned by the U.S. Department of Energy (DOE) are under consideration for decommissioning. Currently, there are no standardized, automated, remote systems designed to dismantle and thereby reduce the size of activated reactor components and vessels so that they can be packaged and shipped to disposal sites. Existing dismantling systems usually consist of customized, facility-specific tooling that has been developed to dismantle a specific reactor system. Such systems have a number of drawbacks. Generally, current systems cannot be disassembled, moved, and reused. Developing and deploying the tooling for current systems is expensive and time-consuming. In addition, the amount of manual work is significant because long-handled tools must be used; as a result, personnel are exposed to excessive radiation. A standardized, automated, remote system is therefore needed to deliver the tooling necessary to dismantle nuclear facilities at different locations. Because this system would be reusable, it would produce less waste. The system would also save money because of its universal design, and it would be more reliable than current systems.

  15. Data Validation Package, June 2016 Groundwater Sampling at the Hallam, Nebraska, Decommissioned Reactor Site, August 2016

    Energy Technology Data Exchange (ETDEWEB)

    Surovchak, Scott [USDOE Office of Legacy Management, Washington, DC (United States); Miller, Michele [Navarro Research and Engineering, Oak Ridge, TN (United States)

    2016-08-01

    The 2008 Long-Term Surveillance Plan [LTSP] for the Decommissioned Hallam Nuclear Power Facility, Hallam, Nebraska (http://www.lm.doe.gov/Hallam/Documents.aspx) requires groundwater monitoring once every 2 years. Seventeen monitoring wells at the Hallam site were sampled during this event as specified in the plan. Planned monitoring locations are shown in Attachment 1, Sampling and Analysis Work Order. Water levels were measured at all sampled wells and at two additional wells (6A and 6B) prior to the start of sampling. Additionally, water levels of each sampled well were measured at the beginning of sampling. See Attachment 2, Trip Report, for additional details. Sampling and analysis were conducted as specified in Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated, http://energy.gov/lm/downloads/sampling-and-analysis-plan-us-department- energy-office-legacy-management-sites). Gross alpha and gross beta are the only parameters that were detected at statistically significant concentrations. Time/concentration graphs of the gross alpha and gross beta data are included in Attachment 3, Data Presentation. The gross alpha and gross beta activity concentrations observed are consistent with values previously observed and are attributed to naturally occurring radionuclides (e.g., uranium and uranium decay chain products) in the groundwater.

  16. Use of multiscale particle simulations in the design of nuclear plant decommissioning

    Institute of Scientific and Technical Information of China (English)

    Richard A. Williams; Xiao dong Jia; Peter Ikin; David Knight

    2011-01-01

    The application of a digital modelling method that can faithfully take account of three-dimensional shape and inherent physical and chemical properties of each particulate component provides an essential tool in decommissioning design.This is useful in handling of high,medium and low level radioactive waste.The processes involve making decisions on where to cut existing plant components and then how to pack these components into boxes,which are then cemented and kept for long term storage as the level of radioactive declines with time.We illustrate the utility of the method and its ability to take data at plant scale (m-scale) and then deduce behaviours at sub millimetre scale in the packed containers.A variety of modelling approaches are used as a part of this approach including cutting algorithms,geometric and dynamic (distinct element) force models,and lattice Boltzmann methods.These methods are applicable to other complex particulate systems including simulation of waste,building recycling,heap leaching and related minerals processes.The paper introduces the basic concepts of this multi-scale and multi-model approach.

  17. Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

    Energy Technology Data Exchange (ETDEWEB)

    Dean, L.N. [Advanced Sciences, Inc., (United States)

    1994-02-01

    Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

  18. Thermal analysis to support decommissioning of the molten salt reactor experiment

    Energy Technology Data Exchange (ETDEWEB)

    Sulfredge, C.D.; Morris, D.G.; Park, J.E.; Williams, P.T.

    1996-06-01

    As part of the decommissioning process for the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory, several thermal-sciences issues were addressed. Apparently a mixture of UF{sub 6} and F{sub 2} had diffused into the upper portion of one charcoal column in the MSRE auxiliary charcoal bed (ACB), leading to radiative decay heating and possible chemical reaction sources. A proposed interim corrective action was planned to remove the water from the ACB cell to reduce criticality and reactivity concerns and then fill the ACB cell with an inert material. This report describes design of a thermocouple probe to obtain temperature measurements for mapping the uranium deposit, as well as development of steady-state and transient numerical models for the heat transfer inside the charcoal column. Additional numerical modeling was done to support filling of the ACB cell. Results from this work were used to develop procedures for meeting the goals of the MSRE Remediation Project without exceeding appropriate thermal limits.

  19. Technical program plan for the transitioning, decommissioning, and final disposition focus area

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    Hundreds of aging nuclear materials processing facilities within the Department of Energy`s (DOE) Weapons Complex are now being shut down and deactivated. These facilities, situated throughout the United States, will require a monumental effort to clean up safely and with minimal environmental insult. Current cleanup technologies tend to be labor intensive and expensive, they produce an unacceptably large volume of waste, and they expose workers to radioactive and other hazardous substances. This document describes an emerging program designed to develop and demonstrate new technical approaches to the decontamination and decommissioning (D&D) program for DOE`s nuclear materials processing facilities. Sponsored by the DOE Office of Technology Development within the Office of Environmental Restoration and Waste Management (EM), the program seeks to integrate the strengths of DOE`s technical, managerial, and systems engineering capabilities with those of industry, universities, and other government agencies. Once developed, these technologies will help to provide US industry with a competitive edge in the worldwide market that exists for improved environmental restoration and D&D services.

  20. Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

  1. In Situ Decommissioning Sensor Network, Meso-Scale Test Bed - Phase 3 Fluid Injection Test Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Serrato, M. G.

    2013-09-27

    The DOE Office of Environmental management (DOE EM) faces the challenge of decommissioning thousands of excess nuclear facilities, many of which are highly contaminated. A number of these excess facilities are massive and robust concrete structures that are suitable for isolating the contained contamination for hundreds of years, and a permanent decommissioning end state option for these facilities is in situ decommissioning (ISD). The ISD option is feasible for a limited, but meaningfull number of DOE contaminated facilities for which there is substantial incremental environmental, safety, and cost benefits versus alternate actions to demolish and excavate the entire facility and transport the rubble to a radioactive waste landfill. A general description of an ISD project encompasses an entombed facility; in some cases limited to the blow-grade portion of a facility. However, monitoring of the ISD structures is needed to demonstrate that the building retains its structural integrity and the contaminants remain entombed within the grout stabilization matrix. The DOE EM Office of Deactivation and Decommissioning and Facility Engineering (EM-13) Program Goal is to develop a monitoring system to demonstrate long-term performance of closed nuclear facilities using the ISD approach. The Savannah River National Laboratory (SRNL) has designed and implemented the In Situ Decommissioning Sensor Network, Meso-Scale Test Bed (ISDSN-MSTB) to address the feasibility of deploying a long-term monitoring system into an ISD closed nuclear facility. The ISDSN-MSTB goal is to demonstrate the feasibility of installing and operating a remote sensor network to assess cementitious material durability, moisture-fluid flow through the cementitious material, and resulting transport potential for contaminate mobility in a decommissioned closed nuclear facility. The original ISDSN-MSTB installation and remote sensor network operation was demonstrated in FY 2011-12 at the ISDSN-MSTB test cube

  2. Effect of Fe(III) on 1,1,2,2-tetrachloroethane degradation and vinyl chloride accumulation in wetland sediments of the Aberdeen proving ground

    Science.gov (United States)

    Jones, E.J.P.; Voytek, M.A.; Lorah, M.M.

    2004-01-01

    1,1,2,2-Tetrachloroethane (TeCA) contaminated groundwater at the Aberdeen Proving Ground discharges through an anaerobic wetland in West Branch Canal Creek, MD, where dechlorination occurred. Two microbially mediated pathways, dichloroelimination and hydrogenolysis, account for most of the TeCA degradation at this site. The dichloroelimination pathways led to the formation of vinyl chloride (VC), a recalcitrant carcinogen of great concern. The effect of adding Fe(III) to TeCA-amended microcosms of wetland sediment was studied. Differences were identified in the TeCA degradation pathway between microcosms treated with amorphous ferric oxyhydroxide (AFO-treated) and untreated (no AFO) microcosms. TeCA degradation was accompanied by a lower accumulation of VC in AFO-treated microcosms than no AFO microcosms. The microcosm incubations and subsequent experiments with the microcosm materials showed that AFO treatment resulted in lower production of VC by shifting TeCA degradation from dichloroelimination pathways to production of a greater proportion of chlorinated ethane products, and decreasing the microbial capability to produce VC from 1,2-dichloroethylene. VC degradation was not stimulated in the presence of Fe(III). Rather, VC degradation occurred readily under methanogenic conditions and was inhibited under Fe(III)-reducing conditions.

  3. Long-term ground-water monitoring program and performance-evaluation plan for the extraction system at the former Nike Missile Battery Site, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Senus, Michael P.; Tenbus, Frederick J.

    2000-01-01

    This report presents lithologic and ground-water-quality data collected during April and May 2000 in the remote areas of the tidal wetland of West Branch Canal Creek, Aberdeen Proving Ground, Maryland. Contamination of the Canal Creek aquifer with volatile organic compounds has been documented in previous investigations of the area. This study was conducted to investigate areas that were previously inaccessible because of deep mud and shallow water, and to support ongoing investigations of the fate and transport of volatile organic compounds in the Canal Creek aquifer. A unique vibracore drill rig mounted on a hovercraft was used for drilling and ground-water sampling. Continuous cores of the wetland sediment and of the Canal Creek aquifer were collected at five sites. Attempts to sample ground water were made by use of a continuous profiler at 12 sites, without well installation, at a total of 81 depths within the aquifer. Of those 81 attempts, only 34 sampling depths produced enough water to collect samples. Ground-water samples from two sites had the highest concentrations of volatile organic compounds?with total volatile organic compound concentrations in the upper part of the aquifer ranging from about 15,000 to 50,000 micrograms per liter. Ground-water samples from five sites had much lower total volatile organic compound concentrations (95 to 2,100 micrograms per liter), whereas two sites were essentially not contaminated, with total volatile organic compound concentrations less than or equal to 5 micrograms per liter.

  4. Lithologic and ground-water-quality data collected using Hoverprobe drilling techniques at the West Branch Canal Creek wetland, Aberdeen Proving Ground, Maryland, April-May 2000

    Science.gov (United States)

    Phelan, Daniel J.; Senus, Michael P.; Olsen, Lisa D.

    2001-01-01

    This report presents lithologic and groundwater- quality data collected during April and May 2000 in the remote areas of the tidal wetland of West Branch Canal Creek, Aberdeen Proving Ground, Maryland. Contamination of the Canal Creek aquifer with volatile organic compounds has been documented in previous investigations of the area. This study was conducted to investigate areas that were previously inaccessible because of deep mud and shallow water, and to support ongoing investigations of the fate and transport of volatile organic compounds in the Canal Creek aquifer. A unique vibracore drill rig mounted on a hovercraft was used for drilling and groundwater sampling. Continuous cores of the wetland sediment and of the Canal Creek aquifer were collected at five sites. Attempts to sample ground water were made by use of a continuous profiler at 12 sites, without well installation, at a total of 81 depths within the aquifer. Of those 81 attempts, only 34 sampling depths produced enough water to collect samples. Ground-water samples from two sites had the highest concentrations of volatile organic compounds?with total volatile organic compound concentrations in the upper part of the aquifer ranging from about 15,000 to 50,000 micrograms per liter. Ground-water samples from five sites had much lower total volatile organic compound concentrations (95 to 2,100 micrograms per liter), whereas two sites were essentially not contaminated, with total volatile organic compound concentrations less than or equal to 5 micrograms per liter.

  5. Contamination of ground water, surface water, and soil, and evaluation of selected ground-water pumping alternatives in the Canal Creek area of Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Lorah, Michelle M.; Clark, Jeffrey S.

    1996-01-01

    Chemical manufacturing, munitions filling, and other military-support activities have resulted in the contamination of ground water, surface water, and soil in the Canal Creek area of Aberdeen Proving Ground, Maryland. Chlorinated volatile organic compounds, including 1,1,2,2-tetrachloroethane and trichloroethylene, are widespread ground-water contaminants in two aquifers that are composed of unconsolidated sand and gravel. Distribution and fate of chlorinated organic compounds in the ground water has been affected by the movement and dissolution of solvents in their dense immiscible phase and by microbial degradation under anaerobic conditions. Detection of volatile organic contaminants in adjacent surface water indicates that shallow contaminated ground water discharges to surface water. Semivolatile organic compounds, especially polycyclic aromatic hydrocarbons, are the most prevalent organic contaminants in soils. Various trace elements, such as arsenic, cadmium, lead, and zinc, were found in elevated concentrations in ground water, surface water, and soil. Simulations with a ground-water-flow model and particle tracker postprocessor show that, without remedial pumpage, the contaminants will eventually migrate to Canal Creek and Gunpowder River. Simulations indicate that remedial pumpage of 2.0 million gallons per day from existing wells is needed to capture all particles originating in the contaminant plumes. Simulated pumpage from offsite wells screened in a lower confined aquifer does not affect the flow of contaminated ground water in the Canal Creek area.

  6. Water-quality and water-level data for a freshwater tidal wetland, West Branch Canal Creek, Aberdeen Proving Ground, Maryland, October 1998-September 1999

    Science.gov (United States)

    Spencer, Tracey A.; Olsen, Lisa D.; Lorah, Michelle M.; Mount, Mastin M.

    2000-01-01

    This report presents water-quality data for ground-water and surface-water samples and water-level data collected by the U.S. Geological Survey from October 1998 through September 1999 at West Branch Canal Creek, Aberdeen Proving Ground, Maryland. The report also provides a description of the sampling and analytical methods that were used to collect and analyze the samples, and includes an evaluation of the quality-assurance data. The ground-water sampling network includes 88 wells or piezometers, including four 2-inch wells, two 4-inch wells, thirty 0.75-inch piezo-meters, and fifty-two 0.25-inch piezometers. Water levels were measured in 105 wells or piezometers. Surface-water samples were collected at five sites. Samples were collected from wells and 0.75-inch piezometers for measurement of field parameters, and analysis of inorganic and organic constituents during three sampling rounds: March, May through June, and July through August of 1999. Inorganic constituents and organic constituents were analyzed in samples collected from 0.25-inch piezometers during three sampling rounds in February through March, May, and September of 1999. Water levels were measured in October and November of 1998, and in February and May of 1999. Surface-water samples were collected between February and August of 1999 for analysis of organic constituents.

  7. New and improved methods for monitoring air quality and the terrestrial environment: Applications at Aberdeen Proving Ground-Edgewood area. Annual report, 1 April--14 November 1997

    Energy Technology Data Exchange (ETDEWEB)

    Bromenshenk, J.J.; Smith, G.C.

    1998-03-01

    Honey bees (Apis mellifera L.) have been shown to be multi-media monitors of chemical exposures and resultant effects. This five-year project has developed an automated system to assess in real-time colony behavioral responses to stressors, both anthropogenic and natural, including inclement weather. Field trials at the Aberdeen Proving Ground-Edgewood included the Old O Field and J field landfills, the Canal Creek and Bush River areas, and a Churchville, MD reference site. Preliminary results show varying concentrations of bioavailable inorganic elements and chlorinated hydrocarbons in bee colonies from all Maryland sites. Industrial solvents in the air inside beehives exhibited the greatest between site differences, with the highest levels occurring in hives near landfills at Old O Field, J Field, and at some sites in the Bush River and Canal Creek areas. Compared to 1996, the 1997 levels of solvents in Old O Field hives decreased by an order of magnitude, and colony performance significantly improved, probably as a consequence of capping the landfill. Recent chemical monitoring accomplishments include development of a new apparatus to quantitatively calibrate TD/GC/MS analysis, a QA/QC assessment of factors that limit the precision of these analyses, and confirmation of transport of aqueous contaminants into the hive. Real-time effects monitoring advances include development of an extensive array of software tools for automated data display, inspection, and numerical analysis and the ability to deliver data from remote locations in real time through Internet or Intranet connections.

  8. On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Kristofova, Kristina; Tatransky, Peter; Zachar, Matej [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2007-03-15

    The presented report is focused on tentative calculations of basic decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by Intermediate storage facility for spent fuel in Studsvik, by means of calculation code OMEGA. This report continuously follows up two previous projects, which described methodology of cost estimates of decommissioning with an emphasis to derive cost functions for alpha contaminated material and implementation of the advanced decommissioning costing methodology for Intermediate Storage facility for Spent Fuel in Studsvik. The main purpose of the presented study is to demonstrate the trial application of the advanced costing methodology using OMEGA code for Intermediate Storage Facility for Spent Fuel in Studsvik. Basic work packages presented in report are as follows: 1. Analysis and validation input data on Intermediate Storage Facility for Spent Fuel and assemble a database suitable for standardised decommissioning cost calculations including radiological parameters, 2. Proposal of range of decommissioning calculations and define an extent of decommissioning activities, 3. Defining waste management scenarios for particular material waste streams from Intermediate Storage Facility for Spent Fuel, 4. Developing standardised cost calculation structure applied for Intermediate Storage Facility for Spent Fuel decommissioning calculation and 5. Performing tentative decommissioning calculations for Intermediate Storage Facility for Spent Fuel by OMEGA code. Calculated parameters of decommissioning are presented in structure according to Proposed Standardized List of Items for Costing Purposes. All parameters are documented and summed up in both table and graphic forms in text and Annexes. The presented report documents availability and applicability of methodology for evaluation of costs and other parameters of decommissioning in a form implemented

  9. Decommissioning of the remediation systems at Waverly, Nebraska, in 2011-2012.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Science Division)

    2012-06-29

    documentation of the CCC/USDA characterization and remediation efforts, including the quarterly monitoring reports, is on the compact disc inside the back cover of this report. The EPA reported on the progress of the remediation systems in a series of five-year reviews (EPA 1993, 1999, 2004, 2009). These reports and other EPA documentation are also on the compact disc inside the back cover of this report, along with the Woodward-Clyde (1986, 1988a,b) documentation cited. Starting in 2006, the analytical results for groundwater (the only medium still being monitored) showed no carbon tetrachloride concentrations above the maximum contaminant level (MCL) of 5.0 g/L. Because the cleanup goals specified in the ROD (EPA 1990) had been met, the EPA removed the site from the NPL in November 2006 (Appendix A). In 2008 the National Pollutant Discharge Elimination System (NPDES) permit for the remediation system was deactivated, and a year later the EPA released its fourth and final five-year report (EPA 2009), indicating that no further action was required for the site and that the site was ready for unlimited use. In 2011-2012, the CCC/USDA decommissioned the remediation systems at Waverly. This report documents the decommission process and closure of the site.

  10. Nuclide Inventory Calculation Using MCNPX for Wolsung Unit 1 Reactor Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Rabir, Mohamad Hairie; Noh, Kyoung Ho; Hah, Chang Joo [KEPCO International Nuclear Graduate School, Daejeon (Korea, Republic of)

    2014-05-15

    The CINDER90 computation process involves utilizing linear Markovian chains to determine the time dependent nuclide densities. The CINDER90 depletion algorithm is implemented the MCNPX code package. The coupled depletion process involves a Monte-Carlo steady-state reaction rate calculation linked to a deterministic depletion calculation. The process is shown in Fig.1. MCNPX runs a steady state calculation to determine the system eigenvalue collision densities, recoverable energies from fission and neutrons per fission events. In order to generate number densities for the next time step, the CINDER90 code takes the MCNPX generated values and performs a depletion calculation. MCNPX then takes the new number densities and caries out a new steady-stated calculation. The process repeats itself until the final time step. This paper describe the preliminary source term and nuclide inventory calculation of Candu single fuel channel using MCNPX, as a part of the activities to support the equilibrium core model development and decommissioning evaluation process of a Candu reactor. The aim of this study was to apply the MCNPX code for source term and nuclide inventory calculation of Candu single fuel channel. Nuclide inventories as a function of burnup will be used to model an equilibrium core for Candu reactor. The core lifetime neutron fluence obtained from the model is used to estimate radioactivity at the stage of decommisioning. In general, as expected, the actinides and fission products build up increase with increasing burnup. Despite the fact that the MCNPX code is still in development we can conclude that the code is capable of obtaining relevant results in burnup and source term calculation. It is recommended that in the future work, the calculation has to be verified on the basis of experimental data or comparison with other codes.

  11. Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition.

  12. Advanced sensing and control techniques to facilitate semi-autonomous decommissioning. 1998 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schalkoff, R.J.; Geist, R.M.; Dawson, D.M.

    1998-06-01

    'This research is intended to advance the technology of semi-autonomous teleoperated robotics as applied to Decontamination and Decommissioning (D and D) tasks. Specifically, research leading to a prototype dual-manipulator mobile work cell is underway. This cell is supported and enhanced by computer vision, virtual reality and advanced robotics technology. This report summarizes work after approximately 1.5 years of a 3-year project. The autonomous, non-contact creation of a virtual environment from an existing, real environment (virtualization) is an integral part of the workcell functionality. This requires that the virtual world be geometrically correct. To this end, the authors have encountered severe sensitivity in quadric estimation. As a result, alternative procedures for geometric rendering, iterative correction approaches, new calibration methods and associated hardware, and calibration quality examination software have been developed. Following geometric rendering, the authors have focused on improving the color and texture recognition components of the system. In particular, the authors have moved beyond first-order illumination modeling to include higher order diffuse effects. This allows us to combine the surface geometric information, obtained from the laser projection and surface recognition components of the system, with a stereo camera image. Low-level controllers for Puma 560 robotic arms were designed and implemented using QNX. The resulting QNX/PC based low-level robot control system is called QRobot. A high-level trajectory generator and application programming interface (API) as well as a new, flexible robot control API was required. Force/torque sensors and interface hardware have been identified and ordered. A simple 3-D OpenGL-based graphical Puma 560 robot simulator was developed and interfaced with ARCL and RCCL to assist in the development of robot motion programs.'

  13. SGN's experience in the field of decommissioning and site cleanup

    Energy Technology Data Exchange (ETDEWEB)

    Fouques, F. [SGN, Montigny-le-Bretonneux, 78182 Saint Quentin-en-Yvelines Cedex (France); Destrait, L. [SGN, 30204 Bagnols sur Ceze Cedex (France)

    2003-07-01

    As early as the 1980's, SGN participated in dismantling projects at CEA and COGEMA plants in France. The experience gained has since been applied to many projects in France and abroad. In close collaboration with the customer, SGN is prime contractor on a cleanup and dismantling project, from preliminary studies and tool and process development to release of the site. SGN's areas of expertise include waste retrieval, decontamination processes, intervention robotics, cutting tools and waste management and treatment. SGN's proposal is based on proven methods and feedback from earlier projects. SGN is currently participating in many cleanup and dismantling projects, including the three (LRTP project at Chernobyl, Marcoule Plant UP1 and Hanford in the U.S.A) presented below. The contents is as follows: 1. Introduction; 2. LRTP Project at Chernobyl; 2.1. Description of interim waste storage; 2.2. Organization; 2.3. Plant characteristics; 2.4. Process Implemented (waste retrieval from the storage tanks; waste sampling and pretreatment; Volume reduction; Cementing); 2.5. Schedule; 3. Marcoule plant UP1; 3.1 Description of plant UP1; 3.2 Organization; 3.3. Cleanup/Dismantling program; 3.3.1. Purpose of the decommissioning and cleanup operations; 3.3.2. D and D techniques Implemented (Cleanup techniques used; Examples of remote handling equipment): 3.3.3. Purpose of the waste retrieval and packaging operations; 3.3.4. Purpose of the dismantling operations; 4. Hanford in the U.S.A.; 4.1. Decontamination and cleanup of hot cells; 4.2. Liquid and sludge retrieval; 4.3. Retrieval and packaging of spent nuclear fuel.

  14. Ecological aspects of decommissioning and decontamination of facilities on the Hanford Reservation

    Energy Technology Data Exchange (ETDEWEB)

    Rickard, W.H.; Klepper, E.L.

    1976-06-01

    The Hanford environment and biota are described in relation to decommissioning of obsolescent facilities contaminated with low-levels of radioactive materials. The aridity at Hanford limits both the productivity and diversity of biota. Both productivity and diversity are increased when water is added, as for example on the margins of ponds. Certain plants, especially Salsola kali (Russian thistle or tumbleweed), are avid accumulators of minerals and will accumulate radioactive materials if their roots come into contact with contaminated soils. Data on concentration ratios (pCi per gDW of plant/pCi per gDW soil) are given for several native plants for long-lived radionuclides. Plants are generally more resistant than animals to ionizing radiation so that impacts of high-level radiation sources would be expected to occur primarily in the animals. Mammals and birds are discussed along with information on where they are to be found on the Reservation and what role they may play in the long-term management of radioactive wastes. Food habits of animals are discussed and plants which are palatable to common herbivores are listed. Food chains leading to man are shown to be very limited, including a soil-plant-mule deer-man path for terrestrial sites and a pond-waterfowl-man pathway for pond sites. Retention basins are discussed as an example of how an ecologically sound decommissioningprogram might be planned. Finally, burial of large volumes of low-level wastes can probably be done if barriers to biological invasion are provided.

  15. Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4. Volume 1: Technology evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    During World War 11, the Oak Ridge Y-12 Plant was built as part of the Manhattan Project to supply enriched uranium for weapons production. In 1945, Building 9201-4 (Alpha-4) was originally used to house a uranium isotope separation process based on electromagnetic separation technology. With the startup of the Oak Ridge K-25 Site gaseous diffusion plant In 1947, Alpha-4 was placed on standby. In 1953, the uranium enrichment process was removed, and installation of equipment for the Colex process began. The Colex process--which uses a mercury solvent and lithium hydroxide as the lithium feed material-was shut down in 1962 and drained of process materials. Residual Quantities of mercury and lithium hydroxide have remained in the process equipment. Alpha-4 contains more than one-half million ft{sup 2} of floor area; 15,000 tons of process and electrical equipment; and 23,000 tons of insulation, mortar, brick, flooring, handrails, ducts, utilities, burnables, and sludge. Because much of this equipment and construction material is contaminated with elemental mercury, cleanup is necessary. The goal of the Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 is to provide a planning document that relates decontamination and decommissioning and waste management problems at the Alpha-4 building to the technologies that can be used to remediate these problems. The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 builds on the methodology transferred by the U.S. Air Force to the Environmental Management organization with DOE and draws from previous technology logic diagram-efforts: logic diagrams for Hanford, the K-25 Site, and ORNL.

  16. Three-dimensional numerical simulations of methane gas migration from decommissioned hydrocarbon production wells into shallow aquifers

    Science.gov (United States)

    Roy, N.; Molson, J.; Lemieux, J.-M.; Van Stempvoort, D.; Nowamooz, A.

    2016-07-01

    Three-dimensional numerical simulations are used to provide insight into the behavior of methane as it migrates from a leaky decommissioned hydrocarbon well into a shallow aquifer. The conceptual model includes gas-phase migration from a leaky well, dissolution into groundwater, advective-dispersive transport and biodegradation of the dissolved methane plume. Gas-phase migration is simulated using the DuMux multiphase simulator, while transport and fate of the dissolved phase is simulated using the BIONAPL/3D reactive transport model. Methane behavior is simulated for two conceptual models: first in a shallow confined aquifer containing a decommissioned leaky well based on a monitored field site near Lindbergh, Alberta, Canada, and secondly on a representative unconfined aquifer based loosely on the Borden, Ontario, field site. The simulations show that the Lindbergh site confined aquifer data are generally consistent with a 2 year methane leak of 2-20 m3/d, assuming anaerobic (sulfate-reducing) methane oxidation and with maximum oxidation rates of 1 × 10-5 to 1 × 10-3 kg/m3/d. Under the highest oxidation rate, dissolved methane decreased from solubility (110 mg/L) to the threshold concentration of 10 mg/L within 5 years. In the unconfined case with the same leakage rate, including both aerobic and anaerobic methane oxidation, the methane plume was less extensive compared to the confined aquifer scenarios. Unconfined aquifers may therefore be less vulnerable to impacts from methane leaks along decommissioned wells. At other potential leakage sites, site-specific data on the natural background geochemistry would be necessary to make reliable predictions on the fate of methane in groundwater.

  17. In-situ determination of radionuclide levels in facilities to be decommissioned using the allowable residual contamination level method

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, R.J.; Haggard, D.L.

    1989-07-01

    This feasibility study resulted in verification of a direct and two alternate indirect techniques for making in-situ determinations of {sup 90}Sr and other radionuclide levels in a Hanford facility to be decommissioned that was evaluated using the Allowable Residual Contamination Level (ARCL) method. The ARCL method is used to determine the extent of decontamination that will be required before a facility can be decommissioned. A sump in the 1608F Building was chosen for the feasibility study. Hanford decommissioning personnel had previously taken 79 concrete and surface scale samples from the building to be analyzed by radiochemical analysis. The results of the radiochemical analyses compare favorably with the values derived by the in-situ methods presented in this report. Results obtained using a portable spectrometer and thermoluminescent dosimeters (TLDs) were both very close to the radiochemistry results. Surface {sup 90}Sr levels detected on the sump floor were 550 pCi/cm{sup 2} using the spectrometer system and 780 pCi/cm{sup 2} using the TLD data. This compares favorably with the levels determined by radiochemical analyses (i.e., 230 to 730 pCi/cm{sup 2}). Surface {sup 90}Sr levels detected on the sump wall ranged between 10 and 80 pCi/cm{sup 2} using the spectrometer system, compared with a conservative 200 pCi/cm{sup 2} using the TLD data. The radiochemical results ranged between 19 and 77 pCi/cm{sup 2} for the four samples taken from the wall at indeterminate locations. 17 refs., 15 figs., 2 tabs.

  18. Estimating boiling water reactor decommissioning costs: A user`s manual for the BWR Cost Estimating Computer Program (CECP) software. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Bierschbach, M.C. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-06-01

    Nuclear power plant licensees are required to submit to the US Nuclear Regulatory Commission (NRC) for review their decommissioning cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personal computer, provides estimates for the cost of decommissioning boiling water reactor (BWR) power stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.

  19. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014); Project Management Unit para el desmantelamiento de CN Bohunice V1 (2003-2014)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Fernandez-conde, A.; Brochet, I.; Ferreira, A.

    2015-07-01

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  20. An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff; Rusch, Chris [NAC International, Atlanta, GA (United States)

    2006-07-15

    This report presents the plans, processes and results of the decontamination and decommissioning of the Hot Cell Facility in Building 23 at the General Atomics Torrey Pines Mesa Facility (HCF) and compares the program and cost of decommissioning HCF with the Swedish cost estimate for decontamination and decommissioning of the HM hot cell and wastes treatment facility at Studsvik in Sweden. The HCF had three main hot cells and was licensed to: Receive, handle and ship radioactive materials; Remotely handle, examine and store irradiated fuel materials; Extract tritium (engineering scale); Support new reactor production development; Develop, fabricate and inspect UO{sub 2} - BeO fuel materials. The HM facility in Studsvik was constructed to handle and package medium-active solid and liquid wastes, prior to disposal. Central to the facility is a conventional hot cell including three work stations, serviced by master slave manipulators. Other parts of the facility include holding tanks for liquid wastes and slurries, a centrifuge room, as well as an encapsulation station where drummed wastes can be encapsulated in cement, offices, laboratories and workshops and so on, as well as building and cell ventilation systems. Decontamination and decommissioning of the HCF took place during 1993 through 2001. The objective was to obtain regulatory release of the site so that it could be used on an unrestricted basis. Based on data from extensive hazardous and radiological materials characterization, GA evaluated four decommissioning options and selected dismantling as the only option that would satisfy the decommissioning objective. The decontamination and decommissioning scope included the following actions. 1. Remove the legacy waste that consisted of radioactive wastes stored at the HCF consisting of 21,434 kg of irradiated fuel material (IFM) that was owned by the US DoE and store the waste in temporary storage set up at the GA site. 2. Actual Decontamination and

  1. Ground-water, surface-water, and bottom-sediment contamination in the O-field area, Aberdeen Proving Ground, Maryland, and the possible effects of selected remedial actions on ground water

    Science.gov (United States)

    Vroblesky, Don A.; Lorah, Michelle M.; Oliveros, James P.

    1995-01-01

    Disposal of munitions and chemical-warfare substances has introduced inorganic and organic contaminants to the ground water, surface water, and bottom sediment at O-Field, in the Edgewood area of Aberdeen Proving Ground, Maryland. Contaminants include chloride, arsenic, transition metals, chlorinated aliphatic hydrocarbons, aromatic compounds, and organosulfur and organophosphorus compounds. The hydrologic effects of several remedial actions were estimated by use of a ground-water-flow model. The remedial actions examined were an impermeable covering, encapsulation, subsurface barriers, a ground-water drain, pumping of wells to manage water levels or to remove contaminated ground water for treatment, and no action.

  2. Microbial Consortia Development and Microcosm and Column Experiments for Enhanced Bioremediation of Chlorinated Volatile Organic Compounds, West Branch Canal Creek Wetland Area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Lorah, Michelle M.; Majcher, Emily H.; Jones, Elizabeth J.; Voytek, Mary A.

    2008-01-01

    Chlorinated solvents, including 1,1,2,2-tetrachloroethane, tetrachloroethene, trichloroethene, carbon tetrachloride, and chloroform, are reaching land surface in localized areas of focused ground-water discharge (seeps) in a wetland and tidal creek in the West Branch Canal Creek area, Aberdeen Proving Ground, Maryland. In cooperation with the U.S. Army Garrison, Aberdeen Proving Ground, Maryland, the U.S. Geological Survey is developing enhanced bioremediation methods that simulate the natural anaerobic degradation that occurs without intervention in non-seep areas of the wetland. A combination of natural attenuation and enhanced bioremediation could provide a remedy for the discharging ground-water plumes that would minimize disturbance to the sensitive wetland ecosystem. Biostimulation (addition of organic substrate or nutrients) and bioaugmentation (addition of microbial consortium), applied either by direct injection at depth in the wetland sediments or by construction of a permeable reactive mat at the seep surface, were tested as possible methods to enhance anaerobic degradation in the seep areas. For the first phase of developing enhanced bioremediation methods for the contaminant mixtures in the seeps, laboratory studies were conducted to develop a microbial consortium to degrade 1,1,2,2-tetrachloroethane and its chlorinated daughter products under anaerobic conditions, and to test biostimulation and bioaugmentation of wetland sediment and reactive mat matrices in microcosms. The individual components required for the direct injection and reactive mat methods were then combined in column experiments to test them under groundwater- flow rates and contaminant concentrations observed in the field. Results showed that both direct injection and the reactive mat are promising remediation methods, although the success of direct injection likely would depend on adequately distributing and maintaining organic substrate throughout the wetland sediment in the seep

  3. Design and Performance of an Enhanced Bioremediation Pilot Test in a Tidal Wetland Seep, West Branch Canal Creek, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Majcher, Emily H.; Lorah, Michelle M.; Phelan, Daniel J.; McGinty, Angela L.

    2009-01-01

    Because of a lack of available in situ remediation methods for sensitive wetland environments where contaminated groundwater discharges, the U.S. Geological Survey, in cooperation with the U.S. Army Garrison, Aberdeen Proving Ground, Maryland, conceived, designed, and pilot tested a permeable reactive mat that can be placed horizontally at the groundwater/surface-water interface. Development of the reactive mat was part of an enhanced bioremediation study in a tidal wetland area along West Branch Canal Creek at Aberdeen Proving Ground, where localized areas of preferential discharge (seeps) transport groundwater contaminated with carbon tetrachloride, chloroform, tetrachloroethene, trichloroethene, and 1,1,2,2-tetrachloroethane from the Canal Creek aquifer to land surface. The reactive mat consisted of a mixture of commercially available organic- and nutrient-rich peat and compost that was bioaugmented with a dechlorinating microbial consortium, WBC-2, developed for this study. Due to elevated chlorinated methane concentrations in the pilot test site, a layer of zero-valent iron mixed with the peat and compost was added at the base of the reactive mat to promote simultaneous abiotic and biotic degradation. The reactive mat for the pilot test area was designed to optimize chlorinated volatile organic compound degradation efficiency without altering the geotechnical and hydraulic characteristics, or creating undesirable water quality in the surrounding wetland area, which is referred to in this report as achieving geotechnical, hydraulic, and water-quality compatibility. Optimization of degradation efficiency was achieved through the selection of a sustainable organic reactive matrix, electron donor, and bioaugmentation method. Consideration of geotechnical compatibility through design calculations of bearing capacity, settlement, and geotextile selection showed that a 2- to 3-feet tolerable thickness of the mat was possible, with 0.17 feet settlement predicted for

  4. Characterization of Preferential Ground-Water Seepage From a Chlorinated Hydrocarbon-Contaminated Aquifer to West Branch Canal Creek, Aberdeen Proving Ground, Maryland, 2002-04

    Science.gov (United States)

    Majcher, Emily H.; Phelan, Daniel J.; Lorah, Michelle M.; McGinty, Angela L.

    2007-01-01

    Wetlands act as natural transition zones between ground water and surface water, characterized by the complex interdependency of hydrology, chemical and physical properties, and biotic effects. Although field and laboratory demonstrations have shown efficient natural attenuation processes in the non-seep wetland areas and stream bottom sediments of West Branch Canal Creek, chlorinated volatile organic compounds are present in a freshwater tidal creek at Aberdeen Proving Ground, Maryland. Volatile organic compound concentrations in surface water indicate that in some areas of the wetland, preferential flow paths or seeps allow transport of organic compounds from the contaminated sand aquifer to the overlying surface water without undergoing natural attenuation. From 2002 through 2004, the U.S. Geological Survey, in cooperation with the Environmental Conservation and Restoration Division of the U.S. Army Garrison, Aberdeen Proving Ground, characterized preferential ground-water seepage as part of an ongoing investigation of contaminant distribution and natural attenuation processes in wetlands at this site. Seep areas were discrete and spatially consistent during thermal infrared surveys in 2002, 2003, and 2004 throughout West Branch Canal Creek wetlands. In these seep areas, temperature measurements in shallow pore water and sediment more closely resembled those in ground water than those in nearby surface water. Generally, pore water in seep areas contaminated with chlorinated volatile organic compounds had lower methane and greater volatile organic compound concentrations than pore water in non-seep wetland sediments. The volatile organic compounds detected in shallow pore water in seeps were spatially similar to the dominant volatile organic compounds in the underlying Canal Creek aquifer, with both parent and anaerobic daughter compounds detected. Seep locations characterized as focused seeps contained the highest concentrations of chlorinated parent compounds

  5. Design and analysis of a natural-gradient ground-water tracer test in a freshwater tidal wetland, West Branch Canal Creek, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Olsen, Lisa D.; Tenbus, Frederick J.

    2005-01-01

    A natural-gradient ground-water tracer test was designed and conducted in a tidal freshwater wetland at West Branch Canal Creek, Aberdeen Proving Ground, Maryland. The objectives of the test were to characterize solute transport at the site, obtain data to more accurately determine the ground-water velocity in the upper wetland sediments, and to compare a conservative, ionic tracer (bromide) to a volatile tracer (sulfur hexafluoride) to ascertain whether volatilization could be an important process in attenuating volatile organic compounds in the ground water. The tracer test was conducted within the upper peat unit of a layer of wetland sediments that also includes a lower clayey unit; the combined layer overlies an aquifer. The area selected for the test was thought to have an above-average rate of ground-water discharge based on ground-water head distributions and near-surface detections of volatile organic compounds measured in previous studies. Because ground-water velocities in the wetland sediments were expected to be slow compared to the underlying aquifer, the test was designed to be conducted on a small scale. Ninety-seven ?-inch-diameter inverted-screen stainless-steel piezometers were installed in a cylindrical array within approximately 25 cubic feet (2.3 cubic meters) of wetland sediments, in an area with a vertically upward hydraulic gradient. Fluorescein dye was used to qualitatively evaluate the hydrologic integrity of the tracer array before the start of the tracer test, including verifying the absence of hydraulic short-circuiting due to nonnatural vertical conduits potentially created during piezometer installation. Bromide and sulfur hexafluoride tracers (0.139 liter of solution containing 100,000 milligrams per liter of bromide ion and 23.3 milligrams per liter of sulfur hexafluoride) were co-injected and monitored to generate a dataset that could be used to evaluate solute transport in three dimensions. Piezometers were sampled 2 to 15 times

  6. Heterosis para el peso y la ganancia de peso desde el nacimiento hasta los 18 meses en el cruce de bovinos aberdeen angus por cebú.

    Directory of Open Access Journals (Sweden)

    Arango Ulloa Astrid Johanna

    2000-06-01

    Full Text Available En la presente investigación se tuvieron en cuenta 2032 observaciones para el análisis de peso al nacimiento, ganancia predestete y peso al destete y 603 para ganancia de peso posdestete y peso a los 18 meses, de machos y hembras nacidas entre 1994 y 1996 en la "Hacienda Cuba", localizada en el municipio de Montelíbano, departamento de Córboba. Para determinar la influencia de los diferentes factores genéticos y no genéticos sobre las variables estudiadas, se utilizó el programa de mínimos cuadrados de Harvey (1988. En los modelos para el peso al nacimiento, ganancia diaria predestete, peso al destete, ganancia diaria posdestete y peso a los 18 meses fueron considerados los siguientes factores: año de nacimiento, época de nacimiento, grupo genético de la cría, (Aberdeen Angus x Cebú y Cebú Comercial,sexo de la cría, mes de destete, época de destete, año de destete, mes de pesaje a los 18 meses. Según el modelo estudiado se tuvieron en cuenta como variables al destete, el peso al nacimiento y el peso ajustado al destete. La mayor parte de los factores no genéticos tuvieron efecto significativo (P<0,05, no siendo significativa la época de destete para el modelo de peso a los 18 meses.

  7. Association of selected SNP with carcass and taste panel assessed meat quality traits in a commercial population of Aberdeen Angus-sired beef cattle

    Directory of Open Access Journals (Sweden)

    Williams John L

    2009-06-01

    Full Text Available Abstract Background The purpose of this study was to evaluate the effects of eight single nucleotide polymorphisms (SNP, previously associated with meat and milk quality traits in cattle, in a population of 443 commercial Aberdeen Angus-cross beef cattle. The eight SNP, which were located within five genes: μ-calpain (CAPN1, calpastatin (CAST, leptin (LEP, growth hormone receptor (GHR and acylCoA:diacylglycerol acyltransferase 1 (DGAT1, are included in various commercial tests for tenderness, fatness, carcass composition and milk yield/quality. Methods A total of 27 traits were examined, 19 relating to carcass quality, such as carcass weight and fatness, one mechanical measure of tenderness, and the remaining seven were sensory traits, such as flavour and tenderness, assessed by a taste panel. Results An SNP in the CAPN1 gene, CAPN316, was significantly associated with tenderness measured by both the tenderometer and the taste panel as well as the weight of the hindquarter, where animals inheriting the CC genotype had more tender meat and heavier hindquarters. An SNP in the leptin gene, UASMS2, significantly affected overall liking, where animals with the TT genotype were assigned higher scores by the panellists. The SNP in the GHR gene was significantly associated with odour, where animals inheriting the AA genotype produced steaks with an intense odour when compared with the other genotypes. Finally, the SNP in the DGAT1 gene was associated with sirloin weight after maturation and fat depth surrounding the sirloin, with animals inheriting the AA genotype having heavier sirloins and more fat. Conclusion The results of this study confirm some previously documented associations. Furthermore, novel associations have been identified which, following validation in other populations, could be incorporated into breeding programmes to improve meat quality.

  8. Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 2: Technology logic diagram

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 2 has been divided into five sections: Characterization, Decontamination, Dismantlement, Robotics/Automation, and Waste Management. Each section contains logical breakdowns of the Y-12 D and D problems by subject area and identifies technologies that can be reasonably applied to each D and D challenge.

  9. Assessment, evaluation, and testing of technologies for environmental restoration, decontamination, and decommissioning and high level waste management. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    Uzochukwu, G.A.

    1997-12-31

    Nuclear and commercial non-nuclear technologies that have the potential of meeting the environmental restoration, decontamination and decommissioning, and high-level waste management objectives are being assessed and evaluated. A detailed comparison of innovative technologies available will be performed to determine the safest and most economical technology for meeting these objectives. Information derived from this effort will be matched with the multi-objectives of the environmental restoration, decontamination and decommissioning, and high-level waste management effort to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the safest and most economical technologies are developed for use at SRS and other DOE sites.

  10. Nuclear Waste Management under Approaching Disaster: A Comparison of Decommissioning Strategies for the German Repository Asse II.

    Science.gov (United States)

    Ilg, Patrick; Gabbert, Silke; Weikard, Hans-Peter

    2016-06-14

    This article compares different strategies for handling low- and medium-level nuclear waste buried in a retired potassium mine in Germany (Asse II) that faces significant risk of uncontrollable brine intrusion and, hence, long-term groundwater contamination. We survey the policy process that has resulted in the identification of three possible so-called decommissioning options: complete backfilling, relocation of the waste to deeper levels in the mine, and retrieval. The selection of a decommissioning strategy must compare expected investment costs with expected social damage costs (economic, environmental, and health damage costs) caused by flooding and subsequent groundwater contamination. We apply a cost minimization approach that accounts for the uncertainty regarding the stability of the rock formation and the risk of an uncontrollable brine intrusion. Since economic and health impacts stretch out into the far future, we examine the impact of different discounting methods and rates. Due to parameter uncertainty, we conduct a sensitivity analysis concerning key assumptions. We find that retrieval, the currently preferred option by policymakers, has the lowest expected social damage costs for low discount rates. However, this advantage is overcompensated by higher expected investment costs. Considering all costs, backfilling is the best option for all discounting scenarios considered.

  11. USE OF CEMENTITIOUS MATERIALS FOR SRS REACTOR FACILITY IN-SITU DECOMMISSIONING - 11620

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Stefanko, D.; Serrato, M.; Blankenship, J.; Griffin, W.; Waymer, J.; Matheny, D.; Singh, D.

    2010-12-07

    The United States Department of Energy (US DOE) concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., producing (reactor facilities), processing (isotope separation facilities) or storing radioactive materials. The Savannah River Site 105-P and 105-R Reactor Facility ISD requires about 250,000 cubic yards of grout to fill the below grade structure. The fills are designed to prevent subsidence, reduce water infiltration, and isolate contaminated materials. This work is being performed as a Comprehensive Environmental Response, Compensations and Liability Act (CERCLA) action and is part of the overall soil and groundwater completion projects for P- and R-Areas. Cementitious materials were designed for the following applications: (1) Below grade massive voids/rooms: Portland cement-based structural flowable fills for - Bulk filling, Restricted placement and Underwater placement. (2) Special below grade applications for reduced load bearing capacity needs: Cellular portland cement lightweight fill (3) Reactor vessel fills that are compatible with reactive metal (aluminum metal) components in the reactor vessels: Calcium sulfoaluminate flowable fill, and Magnesium potassium phosphate flowable fill. (4) Caps to prevent water infiltration and intrusion into areas with the highest levels of radionuclides: Portland cement based shrinkage compensating concrete. A system engineering approach was used to identify functions and requirements of the fill and capping materials. Laboratory testing was performed to identify candidate formulations and develop final design mixes. Scale-up testing was performed to verify material production and placement as well as fresh and cured properties. The 105-P and 105-R ISD projects are currently in progress and are expected to be complete in 2012. The focus of this paper is to describe the (1) grout mixes

  12. The SSI regulations on planning before and during decommissioning of nuclear facilities; Foereskrifter om planering infoer och under avveckling av kaerntekniska anlaeggningar

    Energy Technology Data Exchange (ETDEWEB)

    Efraimsson, Henrik; Lund, Ingemar

    2003-09-01

    This report describes the considerations of the SSI in connection with the promulgation of Regulations on planning before and during decommissioning of nuclear facilities (SSI FS 2002:4). A summary of received comments on the issued draft regulations, including judgements of the SSI, is included.

  13. Decontamination and decommissioning of laboratory solutions enriched uranium (IR-01 b); Descontaminacion y desmantelamiento del laboratorio de soluciones de uranio enriquecido (IR-01b)

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Arocas, P. P.; Sama Colao, J.; Garcia Diaz, A.; Torre Rodriguez, J.; Martinez, A.; Argiles, E.; Garrido Delgado, C.

    2010-07-01

    Completed actions decontamination and decommissioning of the Laboratory of Enriched Uranium Solutions, attached to the Radioactivity lR-0l CIEMAT, was carried out final radiological control of the laboratory. From the documentation generated proceeded to request modification of the IR-01 installation by closing its laboratory IR-01 b.

  14. A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP

    Energy Technology Data Exchange (ETDEWEB)

    Milchikov, A.; Hund, G.; Davidko, M.

    1999-10-20

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

  15. The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S. [Japan Nuclear Cycle Development Inst., Tokai Works, Waste Management and Fuel Cycle Research Center, Tokai, Ibaraki (Japan)

    2001-07-01

    This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

  16. Proteomic profiling of bovine M. longissimus lumborum from Crossbred Aberdeen Angus and Belgian Blue sired steers varying in genetic merit for carcass weight.

    Science.gov (United States)

    Keady, Sarah M; Kenny, David A; Ohlendieck, Kay; Doyle, Sean; Keane, M G; Waters, Sinéad M

    2013-02-01

    Bovine skeletal muscle is a tissue of significant value to the beef industry and global economy. Proteomic analyses offer the opportunity to detect molecular mechanisms regulating muscle growth and intramuscular fat accumulation. The current study aimed to investigate differences in protein abundance in skeletal muscle tissue of cattle from two breeds of contrasting maturity (early vs. late maturing), adiposity, and muscle growth potential, namely, Belgian Blue (BB) × Holstein Friesian and Aberdeen Angus (AA) × Holstein Friesian. Twenty AA (n = 10) and BB (n = 10) sired steers, the progeny of sires of either high or low genetic merit, expressed as expected progeny difference for carcass weight (EPDcwt), and bred through AI, were evaluated as 4 genetic groups, BB-High, BB-Low, AA-High, and AA-Low (n = 5 per treatment). Chemical composition analysis of M. longissimus lumborum showed greater protein and moisture and decreased lipid concentrations for BB-sired compared with AA-sired steers. To investigate the effects of both sire breed and EPDcwt on M. longissimus lumborum, proteomic analysis was performed using 2-dimensional difference gel electrophoresis followed by mass spectrometry. Proteins were identified from their peptide sequences, using the National Center for Biotechnology Information (NCBI) and Swiss-prot databases. Metabolic enzymes involved in glycolysis (glycogen phosphorylase, phosphoglycerate mutase) and the citric acid cycle (aconitase 2, oxoglutarate dehydrogenase) were increased in AA- vs. BB-sired steers. Expression of proteins involved in cell structure, such as myosin light chain isoforms and troponins I and T, were also altered due to sire breed. Furthermore, heat shock protein β-1 and peroxiredoxin 6, involved in cell defense, had increased abundance in muscle of AA-sired relative to BB-sired steers. Protein abundance of glucose-6-phosphate isomerase, enolase-3, and pyruvate kinase was greater in AA-sired animals of High compared with Low

  17. Preliminary assessment of potential well yields and the potential for artificial recharge of the Elm and Middle James aquifers in the Aberdeen area, South Dakota

    Science.gov (United States)

    Emmons, P.J.

    1987-01-01

    A complex hydrologic system exists in the glacial drift overlying the bedrock in the Aberdeen, South Dakota, area. The hydrologic system has been subdivided into three aquifers: the Elm, Middle James, and Deep James. These sand-and-gravel outwash aquifers generally are separated from each other by till or other fine-grained sediments. The Elm aquifer is the uppermost and largest of the aquifers and underlies about 204 sq mi of the study area. The maximum altitude of the top of the Elm aquifer is 1,400 ft and the minimum altitude of the bottom is 1,225 ft. The Middle James aquifer underlies about 172 sq mi of the study area. The maximum altitude of the top of the Middle James aquifer is 1,250 ft and the minimum altitude of the bottom is 1 ,150 ft. The lower-most Deep James aquifer was not evaluated. The quality of the water from the Elm and Middle James aquifer varies considerably throughout the study area. The predominant chemical constituents in the water from the aquifers are sodium and sulfate ions; however, calcium, magnesium, bicarbonate, or chloride may dominate locally. The calculated theoretical total well yield from the Elm and Middle James aquifers ranges from a minimum of 64 cu ft/sec, which may be conservative, to a maximum of 640 cu ft/sec. Based on available data, yields of 100 to 150 cu ft/sec probably can be obtained from properly sited and constructed wells. The feasibility of artificially recharging an aquifer, using the technique of water spreading, depends on the geologic and hydraulic characteristics of the aquifer and of the sediments overlying the aquifer through which the recharge water must percolate. The sites suitable for artificial recharge in the study area were defined as those areas where the average aquifer thickness was > 20 ft and the average thickness of the fine-grained sediments overlying the aquifer was < 10 ft. Using these criteria, about 14 sq mi of the study area are suitable for artificial recharge. Infiltration rates in

  18. Changes in ground-water quality in the Canal Creek Aquifer between 1995 and 2000-2001, West Branch Canal Creek area, Aberdeen Proving Ground, Maryland

    Science.gov (United States)

    Phelan, Daniel J.; Fleck, William B.; Lorah, Michelle M.; Olsen, Lisa D.

    2002-01-01

    Since 1917, Aberdeen Proving Ground, Maryland has been the primary chemical-warfare research and development center for the U.S. Army. Ground-water contamination has been documented in the Canal Creek aquifer because of past disposal of chemical and ordnance manufacturing waste. Comprehensive sampling for volatile organic compounds in ground water by the U.S. Geological Survey in the West Branch Canal Creek area was done in June?October 1995 and June?August 2000. The purpose of this report is (1) to compare volatile organic compound concentrations and determine changes in the ground-water contaminant plumes along two cross sections between 1995 and 2000, and (2) to incorporate data from new piezometers sampled in spring 2001 into the plume descriptions. Along the southern cross section, total concentrations of volatile organic compounds in 1995 were determined to be highest in the landfill area east of the wetland (5,200 micrograms per liter), and concentrations were next highest deep in the aquifer near the center of the wetland (3,300 micrograms per liter at 35 feet below land surface). When new piezometers were sampled in 2001, higher carbon tetrachloride and chloroform concentrations (2,000 and 2,900 micrograms per liter) were detected deep in the aquifer 38 feet below land surface, west of the 1995 sampling. A deep area in the aquifer close to the eastern edge of the wetland and a shallow area just east of the creek channel showed declines in total volatile organic compound concentrations of more than 25 percent, whereas between those two areas, con-centrations generally showed an increase of greater than 25 percent between 1995 and 2000. Along the northern cross section, total concentrations of volatile organic compounds in ground water in both 1995 and 2000 were determined to be highest (greater than 2,000 micrograms per liter) in piezometers located on the east side of the section, farthest from the creek channel, and concentrations were progressively lower

  19. External laundry service. A tool for fleet management and flexible decommissioning; Externer Waescheservice. Ein Werkzeug der zentralen Steuerung und der flexiblen Rueckbauplanung

    Energy Technology Data Exchange (ETDEWEB)

    Brueckner, Guenter [Unitech, Hartford, CT (United States); Schmitt, Burkhard [Unitech, Coevorden (Netherlands); Micklinghoff, Michael

    2014-07-15

    While it is common in other countries such as the USA or Sweden to send out contaminated garments to an external laundering facility, this is not the case in Germany, where the preferred tendency in the nuclear industry is to remain independent from an external service provider. After the US based company 'UniTech' built a laundering facility for controlled area garment in Coevorden, Netherlands, in 1996, German operators began testing this service for decommissioning work. At the time, their justification for this choice was based on the following: - In case of a disrupted delivery the consequences would not be as severe for a nuclear power plant in the process of decommissioning. - Additional investments (evaporators) would have been necessary to install in the laundries of the individual nuclear power plants. - The existing on-site laundries and waste treatment equipment were often not suited to deal with nuclides, specific to decommissioning. It quickly became evident that a specialized service provider could conduct the necessary tasks more effectively, more flexibly, and with higher quality than an ancillary on-site facility. In addition, it became evident that central fleet management tasks are facilitated by contracting an external service provider. Business and technical processes, and requirements agreed upon in a framework agreement, supported the introduction of unified standards. The road map for future decommissioning projects in Germany is impacted by many uncertainties. Therefore, planning requires a great deal of flexibility. Here, as with other related operations, it is critical that enough protective garments are in the right place at the right time. If this does not happen, delays, additional costs and changes to process planning result. For these reasons, an external laundering and garment management service is the most reliable solution. Industry experience shows that even very short-term requests for large quantities of protective

  20. Economic impact associated with the decommissioning process of Vandellos I Nuclear Power Plant; Informe final. Impacto economico del desmantelamiento de la central nuclear Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Silva, M.

    2005-07-01

    This economic study examines the economic impact associated with the decommissioning process of the Vandellos I Nuclear Power Plant, measured in terms of the global income that generated the ending of the Nuclear Power Plant activity, on the territory. To this end, we will take into account the total investment that has been necessary to complete the process of decommissioning. The economic impact is calculated using the Input- Output methodology. Briefly, the Input-Output model defines a group of accounting relationships that reflect the links taking place within the production system. The Input-Output model is based on the assumption that given an increase (decrease) in the final demand of one sector, this sector should produce more (less) to satisfy this new demand. At the same time, this will lead to demand more (less) intermediate consumption goods from the remainder sectors of the economy. Then, these sectors should produce more (less) and use more (less) intermediate inputs, and so on. Therefore, an increase (decrease) in the final demand of one sector multiplies the effect throughout the economy, following the interdependency relationships that exist among the productive activities. We will start by collecting an exhaustive economic information. This information covers the whole decommissioning process and the whole economic and productive activity of the province of Tarragona. Next, this information is used with the objective of building an Input-Output table of the province that will serve as a base to establish the global economic impact of Vandellos I. The incomes and employment generation has been evaluated in the province of Tarragona that, following the main assumptions, correspond to the global effects of the decommissioning. In addition, we have evaluated the income and employment generation within the region where the nuclear power plant is located. The total income impacts show a high multiplier effect due to the investment carried out during the

  1. Decommissioning and Dismantling of the Floating Maintenance Base 'Lepse' - 13316

    Energy Technology Data Exchange (ETDEWEB)

    Field, D.; Mizen, K. [Nuvia Limited (United Kingdom)

    2013-07-01

    The Lepse was built in Russia in 1934 and commissioned as a dry cargo ship. In 1961 she was re-equipped for use as a nuclear service ship (NSS), specifically a floating maintenance base (FMB), to support the operation of the civilian nuclear fleet (ice-breakers) of the USSR. In 1988 Lepse was taken out of service and in 1990 she was re-classified as a 'berth connected ship', located at a berth near the port of Murmansk under the ownership of Federal State Unitary Enterprise (FSUE) Atomflot. Lepse has special storage facilities for spent nuclear fuel assemblies (SFA) that have been used to store several hundred SFAs for nearly 40 years. High and intermediate-level liquid radioactive waste (LRW) is also present in the spent nuclear fuel assembly storage channels, in special tanks and also in the SFA cooling circuit. Many of the SFAs stored in Lepse are classified as damaged and cannot be removed using standard procedures. The removal of the SFA and LRW from the Lepse storage facilities is a hazardous task and requires specially designed tools, equipment and an infrastructure in which these can be deployed safely. Lepse is a significant environmental hazard in the North West of Russia. Storing spent nuclear fuel and high-level liquid radioactive waste on board Lepse in the current conditions is not acceptable with respect to Russian Federation health, safety and environmental standards and with international best practice. The approved concept design for the removal of the SFA and LRW and dismantling of Lepse requires that the ship be transported to Nerpa shipyard where specialist infrastructure will be constructed and equipment installed. One of the main complexities of the Project lies within the number of interested stakeholders involved in the Project. The Lepse project has been high focus on the international stage for many years with previous international efforts failing to make significant progress towards the objective of decommissioning Lepse. The

  2. Development of an In-Situ Decommissioning Sensor Network Test Bed for Structural Condition Monitoring - 12156

    Energy Technology Data Exchange (ETDEWEB)

    Zeigler, Kristine E.; Ferguson, Blythe A. [Savannah River National Laboratory, Aiken, South Carolina 29808 (United States)

    2012-07-01

    The Savannah River National Laboratory (SRNL) has established an In Situ Decommissioning (ISD) Sensor Network Test Bed, a unique, small scale, configurable environment, for the assessment of prospective sensors on actual ISD system material, at minimal cost. The Department of Energy (DOE) is presently implementing permanent entombment of contaminated, large nuclear structures via ISD. The ISD end state consists of a grout-filled concrete civil structure within the concrete frame of the original building. Validation of ISD system performance models and verification of actual system conditions can be achieved through the development a system of sensors to monitor the materials and condition of the structure. The ISD Sensor Network Test Bed has been designed and deployed to addresses the DOE-Environmental Management Technology Need to develop a remote monitoring system to determine and verify ISD system performance. Commercial off-the-shelf sensors have been installed on concrete blocks taken from walls of the P Reactor Building at the Savannah River Site. Deployment of this low-cost structural monitoring system provides hands-on experience with sensor networks. The initial sensor system consists of groutable thermistors for temperature and moisture monitoring, strain gauges for crack growth monitoring, tilt-meters for settlement monitoring, and a communication system for data collection. Baseline data and lessons learned from system design and installation and initial field testing will be utilized for future ISD sensor network development and deployment. The Sensor Network Test Bed at SRNL uses COTS sensors on concrete blocks from the outer wall of the P Reactor Building to measure conditions expected to occur in ISD structures. Knowledge and lessons learned gained from installation, testing, and monitoring of the equipment will be applied to sensor installation in a meso-scale test bed at FIU and in future ISD structures. The initial data collected from the sensors

  3. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, draft report for comment. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J. [Pacific Northwest Lab., Richland, WA (United States)] [and others

    1994-09-01

    On June 27, 1988, the U.S. Nuclear Regulatory Commission (NRC) published in the Federal Register (53 FR 24018) the final rule for the General Requirements for Decommissioning Nuclear Facilities. With the issuance of the final rule, owners and operators of licensed nuclear power plants are required to prepare, and submit to the NRC for review, decommissioning plans and cost estimates. The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s WNP-2, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives, which now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste. Costs for labor, materials, transport, and disposal activities are given in 1993 dollars. Sensitivities of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances are also examined.

  4. Harmonisation of licensing processes for decommissioning. Options and limitations; Genehmigungsverfahren fuer die Stilllegung der deutschen Kernkraftwerke. Konvoi oder Kakophonie?

    Energy Technology Data Exchange (ETDEWEB)

    Raetzke, Christian

    2016-03-15

    The shutdown of eight reactors in Germany in the wake of Fukushima 2011 and the scheduled phase-out of the remaining units in several steps ending 2022 has obviously triggered a wave of applications for decommissioning and dismantling licences. It would seem natural to strive for a harmonised handling of these processes, analogous to the 'convoi' concept which was successfully employed for licensing and construction of the three most recent German NPPs in the 1980s. However, a comparative analysis shows that the motivation of all players is much different from that of earlier times and that harmonisation of licensing processes for dismantling is not as crucial for operators, authorities and technical support organisations as it was for construction.

  5. Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.

  6. NEPA and NHPA- successful decommissioning of historic Manhattan Project properties at Los Alamos National Laboratory, Los Alamos, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    McGehee, E.D.; Pendergrass, A.K.

    1997-05-21

    This paper describes experiences at Los Alamos National Laboratory during the process of planning and executing decommissioning and decontamination activities on a number of properties constructed as part of the Manhattan project. Many of these buildings had been abandoned for many years and were in deteriorating condition, in addition to being contaminated with asbestos, lead based paints and high explosive residues. Due to the age and use of the structures they were evaluated against criteria for the National Register of Historic Places. This process is briefly reviewed, along with the results, as well as actions implemented as a result of the condition and safety of the structures. A number of the structures have been decontaminated and demolished. Planning is still ongoing for the renovation of one structure, and the photographic and drawing records of the properties is near completion.

  7. Project management for the decommissioning and dismantling of nuclear facilities; Projektmanagement fuer Stilllegung und Rueckbau kerntechnischer Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Klasen, Joerg; Wilhelm, Oliver [ENBW Kernkraft GmbH, Neckarwestheim (Germany); Seizer, Burkhard; Schuetz, Tobias [Drees und Sommer, Stuttgart (Germany)

    2015-12-15

    The decommissioning of nuclear power plants is executed in a classic project manner as it is known from other construction projects. It is obvious to use the known portfolio of project management tools. The complexity that is created by the large size of the project in combination with safety requirements of the nuclear industry has to be handled. Complexity can only be managed addressing two main drivers: Prioritization and speed (agility) in project execution. Prioritization can be realized by applying tools like Earned Value Management. A high speed of project execution is established by applying Agile Management like SCRUM-methods. This method is adopted in the context of the cooperation ''Complex Projects'' to the needs of nuclear industry.

  8. Geoelectrical monitoring of simulated subsurface leakage to support high-hazard nuclear decommissioning at the Sellafield Site, UK

    Energy Technology Data Exchange (ETDEWEB)

    Kuras, Oliver, E-mail: oku@bgs.ac.uk [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Wilkinson, Paul B.; Meldrum, Philip I.; Oxby, Lucy S. [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Uhlemann, Sebastian [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); ETH-Swiss Federal Institute of Technology, Institute of Geophysics, Sonneggstr. 5, 8092 Zurich (Switzerland); Chambers, Jonathan E. [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Binley, Andrew [Lancaster Environment Centre, Lancaster University, Lancaster LA1 4YQ (United Kingdom); Graham, James [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG (United Kingdom); Smith, Nicholas T. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG (United Kingdom); School of Earth, Atmospheric and Environmental Sciences, Williamson Building, University of Manchester, Oxford Road, Manchester M13 9PL (United Kingdom); Atherton, Nick [Sellafield Ltd, Albion Square, Swingpump Lane, Whitehaven CA28 7NE (United Kingdom)

    2016-10-01

    A full-scale field experiment applying 4D (3D time-lapse) cross-borehole Electrical Resistivity Tomography (ERT) to the monitoring of simulated subsurface leakage was undertaken at a legacy nuclear waste silo at the Sellafield Site, UK. The experiment constituted the first application of geoelectrical monitoring in support of decommissioning work at a UK nuclear licensed site. Images of resistivity changes occurring since a baseline date prior to the simulated leaks revealed likely preferential pathways of silo liquor simulant flow in the vadose zone and upper groundwater system. Geophysical evidence was found to be compatible with historic contamination detected in permeable facies in sediment cores retrieved from the ERT boreholes. Results indicate that laterally discontinuous till units forming localized hydraulic barriers substantially affect flow patterns and contaminant transport in the shallow subsurface at Sellafield. We conclude that only geophysical imaging of the kind presented here has the potential to provide the detailed spatial and temporal information at the (sub-)meter scale needed to reduce the uncertainty in models of subsurface processes at nuclear sites. - Graphical abstract: 3D fractional resistivity change (resistivity change Δρ divided by baseline resistivity ρ{sub 0}) image showing results of Stage 1 silo liquor simulant injection. The black line delineates the preferential flow path; green cylinders show regions of historic contamination found in sediment cores from ERT boreholes. - Highlights: • 4D geoelectrical monitoring at Sellafield detected and tracked simulated silo leaks. • ERT revealed likely pathways of silo liquor simulant flow in the subsurface. • The method can reduce uncertainty in subsurface process models at nuclear sites. • Has been applied in this form at a UK nuclear licensed site for the first time • Study demonstrates value of 4D geophysics for nuclear decommissioning.

  9. Rosie - mobile robot worksystem for decommissioning and dismantling operations. Final report, April 1, 1996--January 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    RedZone Robotics, Inc. has undertaken development of an advanced remote worksystem - Rosie - specifically designed to meet the challenges of performing a wide range of decontamination and dismantlement (D&D) operations in nuclear environments. The Rosie worksystem includes a locomotor, heavy manipulator, operator console, and control system for remote operations. The locomotor is a highly mobile platform with tether management and hydraulic power onboard. The heavy manipulator is a high-payload, long-reach boom used to deploy a wide variety of tools and/or sensors into the work area. Rosie`s advanced control system, broad work capabilities, and hardening/reliability for hazardous duty make it a new and unique capability that facilitates completion of significant cleanup projects throughout the Department of Energy (DOE) and private sector. Endurance testing of the first Rosie system from September 1995 to March 1996 has proven its capabilities and appropriateness for D&D applications. Design enhancements were incorporated into the second Rosie system to improve and add features necessary for deployment at a DOE facility decommissioning. This second Rosie unit was deployed to the Argonne National Laboratory`s CP-5 reactor facility in early December 1996, and it is currently being used in the decommissioning of the reactor there. This report will overview this second Rosie system and the design enhancements made to it based on the lessons learned during the design, fabrication, and testing of the first Rosie system. The Rosie system has been designed to be a versatile and adaptable tool that can be used in many different applications in D&D work at nuclear facilities. It can carry a wide variety of tooling, sensors, and other robotic equipment at the tip of its heavy manipulator, and it can deploy those items to many different hazardous work areas. Rosie`s capabilities and system design address the need for durability and reliability in these environments.

  10. Plutonium, americium and radiocaesium in the marine environment close to the Vandellos I nuclear power plant before decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez-Cabeza, J.A. E-mail: joanalbert.sanchez@uab.es; Molero, J

    2000-11-01

    The Vandellos nuclear power plant (NPP), releasing low-level radioactive liquid waste to the Mediterranean Sea, is the first to be decommissioned in Spain, after an incident which occurred in 1989. The presence, distribution and uptake of various artificial radionuclides (radiocaesium, plutonium and americium) in the environment close to the plant were studied in seawater, bottom sediments and biota, including Posidonia oceanica, fish, crustaceans and molluscs. Seawater, sediments and Posidonia oceanica showed enhanced levels in the close vicinity of the NPP, although the effect was restricted to its near environment. Maximum concentrations in seawater were 11.6{+-}0.5 Bq m{sup -3} and 16.9{+-}1.2 mBq m{sup -3} for {sup 137}Cs and {sup 239,240}Pu, respectively. When sediment concentrations were normalized to excess {sup 210}Pb, they showed both the short-distance transport of artificial radionuclides from the Vandellos plant and the long-distance transport of {sup 137}Cs from the Asco NPP. Posidonia oceanica showed the presence of various gamma-emitters attributed to the impact of the Chernobyl accident, on which the effect of the NPP was superimposed. Seawater, sediment and Posidonia oceanica collected near the plant also showed an enhancement of the plutonium isotopic ratio above the fallout value. The uptake of these radionuclides by marine organisms was detectable but limited. Pelagic fish showed relatively higher {sup 137}Cs concentrations and only in the case of demersal fish was the plutonium isotopic ratio increased. The reported levels constitute a set of baseline values against which the impact of the decommissioning operations of the Vandellos I NPP can be studied.

  11. Parâmetros genéticos e tendências genéticas e fenotípicas para escores visuais na fase pós-desmama de bovinos da raça Aberdeen Angus Genetic parameters and genetic and phenotypic trends for post weaning visual scores in Aberdeen Angus breed cattle

    Directory of Open Access Journals (Sweden)

    Tomás Weber

    2009-06-01

    Full Text Available Neste trabalho, foram avaliados, na fase de pós-desmama, 28.349 animais da raça Aberdeen Angus, nascidos entre os anos de 1993 e 2003 e criados em 141 fazendas. Os objetivos deste trabalho foram estimar parâmetros genéticos e avaliar a tendência genética e a fenotípica para os escores de avaliação visual (EVs, conformação (C, precocidade (P, musculatura (M e tamanho (T. Os componentes de (covariância foram estimados por REML, utilizando um modelo animal. As estimativas de herdabilidade foram: 0,13; 0,11; 0,16 e 0,13 para C, P, M e T, respectivamente. As correlações genéticas obtidas entre os escores visuais variaram de 0,01 a 0,92. As tendências genéticas e fenotípicas para C, P, M e T (pontos/ano foram: 0,0054 e 0,0189; 0,0035 e -0,0013; 0,0057 e 0,0217 e 0,0026 e -0,0016, respectivamente. As herdabilidades estimadas sugerem baixa resposta à seleção direta. As correlações genéticas entre os EVs foram altas entre C, P e M (0,79 a 0,92 e foram baixas entre estes e T (0,01 a 0,30. As tendências genéticas mostram que a seleção está promovendo ganho genético de pequena magnitude, porém, as tendências fenotípicas, com valores negativos para algumas características, indicam que deve ser dada mais atenção para as condições ambientais.There were evaluated at post weaning phase, 28.349 Aberdeen Angus breed animals, born from 1993 to 2003 on 141 farms, to estimate genetic parameters and to evaluate genetic and phenotypic trends for visual scores (EVs conformation (C, precocity (P, musculature (M and size (T. The covariance components were obtained by REML using an animal model. The heritabilities estimated were: 0.13, 0.11, 0.16 and 0.13, to C, P, M and T, respectively. The genetic correlations between the EVs range from 0.01 to 0.92. The genetic and phenotypic trends estimated for C, P, M, and T (points/year were 0.0054 and 0.0189; 0.0035 and -0.0013; 0.0057 and 0.0217; and 0.0026 and -0.0016, respectively. The

  12. International Conference on Promotion of the Global Application of Decommissioning and Environmental Restoration Programmes; Conferencia Internacional sobre el Fomento de la Aplicacion global de Programas de Clausura y Restauracion Medioambiental

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-08-01

    The Conference on Promotion of the Global Application of Decommissioning and Environmental Restoration Programmes, organised by the International Atomic Energy Agency (IAEA) with CSN participation, was held in Madrid between May 23rd and 27th. (Author)

  13. Sir John Struthers (1823-1899), Professor of Anatomy in the University of Aberdeen (1863-1889), President of the Royal College of Surgeons of Edinburgh (1895-1897).

    Science.gov (United States)

    Kaufman, M H

    2015-11-01

    Between 1841 and 1845 John Struthers attended both the University of Edinburgh and some of the various Extra-mural Schools of Medicine associated with Surgeons' Hall. While a medical student he became a Member of the Hunterian Medical Society of Edinburgh and later was elected one of their Annual Presidents. He graduated with the MD Edin and obtained both the LRCS Edin and the FRCS Edin diplomas in 1845. Shortly afterwards he was invited to teach Anatomy in Dr Handyside's Extra-mural School in Edinburgh. The College of Surgeons certified him to teach Anatomy in October 1847. He had two brothers, and all three read Medicine in Edinburgh. His younger brother, Alexander, died of cholera in the Crimea in 1855 while his older brother James, who had been a bachelor all his life, practised as a Consultant Physician in Leith Hospital, Edinburgh, until his death.When associated with Dr Handyside's Extra-mural School in Edinburgh, John taught Anatomy there until he was elected to the Chair of Anatomy in Aberdeen in 1863. Much of his time was spent in Aberdeen teaching Anatomy and in upgrading the administrative facilities there. He resigned from this Chair in 1889 and subsequently was elected President of Leith Hospital from 1891 to 1897. This was in succession to his older brother, James, who had died in 1891. Later, he was elected President of the Royal College of Surgeons of Edinburgh from 1895 to 1897 and acted as its Vice-President from 1897 until his death in 1899. In 1898, Queen Victoria knighted him. His youngest son, John William Struthers, was the only one of his clinically qualified sons to survive him and subsequently was elected President of the Edinburgh College of Surgeons from 1941 to 1943.

  14. Decommissioning of the NPP Obrigheim (KWO). Shutdown/close-down of systems or components; Stilllegungsbetrieb der Anlage KWO Obrigheim. Ausserbetriebnahme / Stillsetzung von Systemen oder Anlagenteilen

    Energy Technology Data Exchange (ETDEWEB)

    Rausch, Eberhard H. [ISE Ingenieurgesellschaft fuer Stilllegung und Entsorgung mbH, Roedermark (Germany); Rudolf, Dieter [Energie Baden-Wuerttemberg AG (EnBW), Karlsruhe (Germany)

    2012-11-01

    As a consequence of the decommissioning of the NPP Obrigheim (KWO) the plant was transferred into the decommissioning operation, including the operation of several safety relevant systems and the storage of irradiation fuel elements. Actually, the fuel element have been removed from the reactor pressure vessel and the reactor building 01 and are now stored in an external fuel element storage pool at the NPP site. Most of the systems required for power operation have been shutdown (drained, depressurized, cold, and disconnected from operated systems). The operated systems exhibit significantly lower working pressure and temperatures compared to power operation. The shutdown is performed stepwise, for each system a shutdown plan has to be prepared, describing the scheduled measures. The presentation includes details of the work flow of the performed and planned system shutdown.

  15. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1A: Citations with abstracts, sections 1 through 9

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  16. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1B: Citations with abstracts, sections 10 through 16

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  17. 国外铀矿冶设施的退役治理%Decommissioning and disposal of foreign uranium mine and mill facilities

    Institute of Scientific and Technical Information of China (English)

    潘英杰; 徐乐昌; 薛建新; 袁柏祥

    2012-01-01

    Disposal techniques in decommissioning of foreign uranium mine and mill facilities are systematically discussed, including covering of uranium tailing impoundment, drainaging and consolidation of uranium tailing,and treatment of mining waste water and polluted groundwater.and the costs associated with disposal are analyzed. The necessity of strengthening the decommissioning disposal technology research and international exchanges and cooperation is emphasized.%系统论述了国外铀矿冶设施退役的治理技术,包括铀尾矿库覆盖治理、铀尾矿的排水固结、矿山废水和污染地下水治理等,并分析了相关的治理费用,强调了加强退役治理技术研究与国际交流与合作的必要性.

  18. The SSI project on decommissioning of nuclear plants - a preliminary study; SSI:s projekt avseende avveckling av kaerntekniska anlaeggningar - en foerstudie

    Energy Technology Data Exchange (ETDEWEB)

    Efraimsson, Henrik; Ehdwall, H.; Godaas, T.; Hofvander, P.; Lindhe, J.C.; Lumpus, J.; Lund, I.; Malmqvist, L.; Welleman, E

    1999-01-01

    SSI will amend and complete regulations and stipulations for nuclear plants in order to take into account issues which arise in connection with decommissioning. The objective of a pilot study, performed during 1998, was to identify the questions at issue, what the authority should control and how SSI should proceed with the work. The recommendations and the result of the pilot study are presented in this report 29 refs.

  19. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence and decommissioning experience and Waste management solutions

    Energy Technology Data Exchange (ETDEWEB)

    Salnikova, Tatiana [AREVA GmbH, Erlangen (Germany); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

    2016-10-15

    Summary report on the Key Topics ''Enhanced Safety and Operation Excellence'' and ''Decommissioning Experience and Waste Management Solutions'' of the 47{sup th} Annual Conference on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  20. An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff; Rusch, Chris [NAC International, Atlanta, GA (United States)

    2006-07-15

    This report presents the plans, processes and results of the decontamination and decommissioning of the Hot Cell Facility in Building 23 at the General Atomics Torrey Pines Mesa Facility (HCF) and compares the program and cost of decommissioning HCF with the Swedish cost estimate for decontamination and decommissioning of the HM hot cell and wastes treatment facility at Studsvik in Sweden. The HCF had three main hot cells and was licensed to: Receive, handle and ship radioactive materials; Remotely handle, examine and store irradiated fuel materials; Extract tritium (engineering scale); Support new reactor production development; Develop, fabricate and inspect UO{sub 2} - BeO fuel materials. The HM facility in Studsvik was constructed to handle and package medium-active solid and liquid wastes, prior to disposal. Central to the facility is a conventional hot cell including three work stations, serviced by master slave manipulators. Other parts of the facility include holding tanks for liquid wastes and slurries, a centrifuge room, as well as an encapsulation station where drummed wastes can be encapsulated in cement, offices, laboratories and workshops and so on, as well as building and cell ventilation systems. Decontamination and decommissioning of the HCF took place during 1993 through 2001. The objective was to obtain regulatory release of the site so that it could be used on an unrestricted basis. Based on data from extensive hazardous and radiological materials characterization, GA evaluated four decommissioning options and selected dismantling as the only option that would satisfy the decommissioning objective. The decontamination and decommissioning scope included the following actions. 1. Remove the legacy waste that consisted of radioactive wastes stored at the HCF consisting of 21,434 kg of irradiated fuel material (IFM) that was owned by the US DoE and store the waste in temporary storage set up at the GA site. 2. Actual Decontamination and

  1. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Main report, draft report for comment. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J. [Pacific Northwest Lab., Richland, WA (United States)] [and others

    1994-09-01

    On June 27, 1988, the U.S. Nuclear Regulatory Commission (NRC) published in the Federal Register (53 FR 24018) the final rule for the General Requirements for Decommissioning Nuclear Facilities. With the issuance of the final rule, owners and operators of licensed nuclear power plants are required to prepare, and submit to the NRC for review, decommissioning plans and cost estimates. The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB alternatives, which now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste. Costs for labor, transport, and disposal activities are given in 1993 dollars. Sensitivities of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances are also examined.

  2. Planning, organizational and management issues in moving from operation to decommissioning and their impact on waste management; Temas de planificacion, organizacion y gestion asociados con la transicion de la fase operativa a la clausura y su impacto sobre la gestion de residuos

    Energy Technology Data Exchange (ETDEWEB)

    Laraia, M.

    2001-07-01

    The transition from a nuclear facility's operating phase to decommissioning is critical. A number of modifications are required during this period to adapt the facility to new objectives and requirements. There are various activities to prepare for implementation of the decommissioning strategy that may be started before final plant closure or immediately afterwards: these serve to support the decommissioning planning process and ease the burden of operating requirements. (Author)

  3. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 10 - PRESENTATION OF THE DECOMMISSIONING DEVICE OPERATING

    Directory of Open Access Journals (Sweden)

    Constantin D. STANESCU,

    2015-05-01

    Full Text Available This paper presents a solution proposed by the authors in order to achieve of a cutting and extracting device operating panel for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The Cutting and Extraction Device (CED is fully automated, connected by wires to a Programmable Logic Controller (PLC and controlled from a Human Machine Interface (HMI. The Cutting and Extraction Device (CED performs the dismantling, cutting and extraction of the fuel channel components, moving with variable speed, temperature monitoring and video surveillance inside the pipe, unblock and extract the channel closure plug (from End Fitting - EF, unblock and extract the channel shield plug (from Lattice Tube - LT, block and cut the middle of the pressure tube, block and cut the end of the pressure tube, block and extract the half of pressure tube. All operations can be monitored and controlled from a operating panel. The PLC fully command the device in automatic or manually mode, to control the internal sensors, transducers, electrical motors, video surveillance and pyrometers for monitoring cutting place temperature. The device controller has direct access to the measured values with these sensors, interprets and processes them, preparing the next actionafter confirming the action in progress. The design of the Cutting and Extraction Device (CED shall be achieved according to the particular features of the fuel channel components to be dismantled and to ensure radiation protection of workers.

  4. Decommissioning end of life oilfield facilities and pipelines : the first step to the safe and efficient remediation of oil and gas sites

    Energy Technology Data Exchange (ETDEWEB)

    Kitchen, J.; Thygesen, S. [JSK Consulting Ltd., Red Deer, AB (Canada)

    2005-06-30

    Environmentally sound decommissioning practices in the remediation and reclamation process were reviewed, with reference to abandoned oil and gas facilities and pipelines. There are inherent dangers associated with aged infrastructure, and decommissioning companies should be the first service on site to ensure that all facilities have been located, removed and cleaned. All licensed, unlicensed and on-lease pipelines are required to be properly abandoned. Site research is needed to identify any industry or government regulated requirements that may impact the decommissioning process. Decommissioning companies are also responsible for recording all relevant site information so that it can be conveyed to remediation and reclamation companies. A knowledge of landowner sensitivities, weather affected access, unlicensed facilities and locations of historic contamination are crucial to all parties involved. Additional documentation, such as photographs and survey drawings, can assist remediation and reclamation companies in locating areas of concern. Once a well has been abandoned in Alberta, surface equipment, cement pads, debris and produced liquids associated with the well license must be removed within 12 months of the cutting and capping operation. Records of the removal and cleanup activities must be retained by the licensee. Many sites have been sitting dormant for several years and can be harboring dangerous production fluids, asbestos, Hantavirus and other hazardous materials. All equipment must be steam-cleaned by qualified personnel and all production fluids and contaminated water from the cleaning process must be captured and transported to a waste facility. All equipment that is deemed re-usable can be returned to inventory or re-used. Equipment that can not be salvaged is sold for recycling at a steel mill. All pipelines are required to be cleaned of hydrocarbons, purged and left with a medium of inert gas or atmospheric air. Residual fluids left in a

  5. NEW MATERIALS DEVELOPED TO MEET REGULATORY AND TECHNICAL REQUIREMENTS ASSOCIATED WITH IN-SITU DECOMMISSIONING OF NUCLEAR REACTORS AND ASSOCIATED FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Blankenship, J.; Langton, C.; Musall, J.; Griffin, W.

    2012-01-18

    For the 2010 ANS Embedded Topical Meeting on Decommissioning, Decontamination and Reutilization and Technology, Savannah River National Laboratory's Mike Serrato reported initial information on the newly developed specialty grout materials necessary to satisfy all requirements associated with in-situ decommissioning of P-Reactor and R-Reactor at the U.S. Department of Energy's Savannah River Site. Since that report, both projects have been successfully completed and extensive test data on both fresh properties and cured properties has been gathered and analyzed for a total of almost 191,150 m{sup 3} (250,000 yd{sup 3}) of new materials placed. The focus of this paper is to describe the (1) special grout mix for filling the P-Reactor vessel (RV) and (2) the new flowable structural fill materials used to fill the below grade portions of the facilities. With a wealth of data now in hand, this paper also captures the test results and reports on the performance of these new materials. Both reactors were constructed and entered service in the early 1950s, producing weapons grade materials for the nation's defense nuclear program. R-Reactor was shut down in 1964 and the P-Reactor in 1991. In-situ decommissioning (ISD) was selected for both facilities and performed as Comprehensive Environmental Response, Compensations and Liability Act actions (an early action for P-Reactor and a removal action for R-Reactor), beginning in October 2009. The U.S. Department of Energy concept for ISD is to physically stabilize and isolate intact, structurally robust facilities that are no longer needed for their original purpose of producing (reactor facilities), processing (isotope separation facilities), or storing radioactive materials. Funding for accelerated decommissioning was provided under the American Recovery and Reinvestment Act. Decommissioning of both facilities was completed in September 2011. ISD objectives for these CERCLA actions included: (1) Prevent

  6. Final report on decommissioning of wells, boreholes, and tiltmeter sites, Gulf Coast Interior Salt Domes of Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    In the late 1970s, test holes were drilled in northern Louisiana in the vicinity of Vacherie and Rayburn`s Salt Domes as part of the Department of Energy`s (DOE) National Waste Terminal Storage (NWTS) (rename the Civilian Radioactive Waste Management (CRWM)) program. The purpose of the program was to evaluate the suitability of salt domes for long term storage or disposal of high-level nuclear waste. The Institute for Environmental Studies at Louisiana State University (IES/LSU) and Law Engineering Testing Company (LETCo) of Marietta, Georgia performed the initial field studies. In 1982, DOE awarded a contract to the Earth Technology Corporation (TETC) of Long Beach, California to continue the Gulf Coast Salt Dome studies. In 1986, DOE deferred salt domes from further consideration as repository sites. This report describes test well plugging and site abandonment activities performed by SWEC in accordance with Activity Plan (AP) 1--3, Well Plugging and Site Restoration of Work Sites in Louisiana. The objective of the work outlined in this AP was to return test sites to as near original condition as possible by plugging boreholes, removing equipment, regrading, and seeding. Appendices to this report contain forms required by State of Louisiana, used by SWEC to document decommissioning activities, and pertinent documentation related to lease/access agreements.

  7. Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors - Volume I.

    Energy Technology Data Exchange (ETDEWEB)

    Gauntt, Randall O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mattie, Patrick D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysis (UA) on the Fukushima Daiichi unit (1F1) accident progression with the MELCOR code. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). That study focused on reconstructing the accident progressions, as postulated by the limited plant data. This work was focused evaluation of uncertainty in core damage progression behavior and its effect on key figures-of-merit (e.g., hydrogen production, reactor damage state, fraction of intact fuel, vessel lower head failure). The primary intent of this study was to characterize the range of predicted damage states in the 1F1 reactor considering state of knowledge uncertainties associated with MELCOR modeling of core damage progression and to generate information that may be useful in informing the decommissioning activities that will be employed to defuel the damaged reactors at the Fukushima Daiichi Nuclear Power Plant. Additionally, core damage progression variability inherent in MELCOR modeling numerics is investigated.

  8. Geoelectrical monitoring of simulated subsurface leakage to support high-hazard nuclear decommissioning at the Sellafield Site, UK.

    Science.gov (United States)

    Kuras, Oliver; Wilkinson, Paul B; Meldrum, Philip I; Oxby, Lucy S; Uhlemann, Sebastian; Chambers, Jonathan E; Binley, Andrew; Graham, James; Smith, Nicholas T; Atherton, Nick

    2016-10-01

    A full-scale field experiment applying 4D (3D time-lapse) cross-borehole Electrical Resistivity Tomography (ERT) to the monitoring of simulated subsurface leakage was undertaken at a legacy nuclear waste silo at the Sellafield Site, UK. The experiment constituted the first application of geoelectrical monitoring in support of decommissioning work at a UK nuclear licensed site. Images of resistivity changes occurring since a baseline date prior to the simulated leaks revealed likely preferential pathways of silo liquor simulant flow in the vadose zone and upper groundwater system. Geophysical evidence was found to be compatible with historic contamination detected in permeable facies in sediment cores retrieved from the ERT boreholes. Results indicate that laterally discontinuous till units forming localized hydraulic barriers substantially affect flow patterns and contaminant transport in the shallow subsurface at Sellafield. We conclude that only geophysical imaging of the kind presented here has the potential to provide the detailed spatial and temporal information at the (sub-)meter scale needed to reduce the uncertainty in models of subsurface processes at nuclear sites.

  9. Effect of the decommissioned Roger open dump, João Pessoa, Brazil, on local groundwater quality

    Directory of Open Access Journals (Sweden)

    Giulliano de Souza Fagundes

    2009-04-01

    Full Text Available Throughout 45 years (1958-2003 the solid wastes from João Pessoa were disposed off in the former Roger’s open dump, which is situated adjacent to the mangrove at the sides of Sanhauá river, intensifying environmental problems and threatening the health of people living nearby. Between 1999 and 2003 the decommissioned open dump received wastes from the cities of Cabedelo and Bayeux. Several environmental impacts result from this inadequate disposal of solid wastes, including the pollution of groundwater nearby the former Roger´s open dump, which is the major point of investigation of this paper. The water quality of 6 wells situated in the region of influence of the open dump were monitored. Results have shown that the groundwater near the open dump cannot be drunk by the population without previous treatment, since it has some parameters of water quality in discordance with Brazilian legislation concerned with drinking water. Results have also shown that the level of pollution is higher in the wells closer to the open dump.

  10. BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Stefanko, D.

    2011-03-10

    The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010].

  11. Final report of the decontamination and decommissioning of Building 44 at the Grand Junction Projects Office Facility

    Energy Technology Data Exchange (ETDEWEB)

    Widdop, M.R.

    1996-07-01

    The U.S. Department of Energy (DOE) Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial action contractor. Building 44 was radiologically contaminated and the building was demolished in 1994. The soil area within the footprint of the building was not contaminated; it complies with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.

  12. Final report of the decontamination and decommissioning of Building 1 at the Grand Junction Projects Office Facility

    Energy Technology Data Exchange (ETDEWEB)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 1 was found to be radiologically contaminated and was demolished in 1996. The soil beneath and adjacent to the building was remediated in accordance with identified standards and can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.

  13. Final report of the decontamination and decommissioning of Building 18 at the Grand Junction Projects Office Facility

    Energy Technology Data Exchange (ETDEWEB)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. The soil beneath Building 18 was found to be radiologically contaminated; the building was not contaminated. The soil was remediated in accordance with identified standards. Building 18 and the underlying soil can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.

  14. Final report of the decontamination and decommissioning of Building 34 at the Grand Junction Projects Office Facility

    Energy Technology Data Exchange (ETDEWEB)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, was also the remedial action contractor. Building 34 was radiologically contaminated and the building was demolished in 1996. The soil area within the footprint of the building was analyzed and found to be not contaminated. The area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual closeout report for each contaminated GJPO building.

  15. Eficiência produtiva em vacas primíparas das raças Aberdeen Angus e Charolês Productive efficiency of Angus and Charolais primiparous cows

    Directory of Open Access Journals (Sweden)

    Edson Luis de Azambuja Ribeiro

    2001-02-01

    Full Text Available Este trabalho foi conduzido com o objetivo de avaliar o desempenho produtivo de vacas de corte. Foram utilizadas 30 vacas da raça Aberdeen Angus e 32 da raça Charolês primíparas, prenhes no início do experimento, com bezerros puros ou mestiços Nelore. As vacas foram submetidas a diferentes tratamentos alimentares durante o inverno e a primavera: T1 - pastagem natural, T2 - pastagem cultivada por 60 dias (24 horas/dia, do início de setembro ao início de novembro, T3 - acesso à pastagem cultivada por duas horas diárias, por um período de 60 dias (de início de julho ao início de setembro, T4 - acesso à pastagem cultivada por duas horas diárias, por um período de 60 dias (de início de julho ao início de setembro, e mais 60 dias (24 horas/dia de pastagem cultivada do início de setembro ao início de novembro. As medidas de eficiência produtiva foram: EPPARTO = (P205/PVP*100; EPDESMAME = (P205/PVD*100; EPMBPARTO = (P205/PVP0,75; EPMBDESMAME = (P205/PVD0,75; e EPNDT = NDTTOTAL/P205, em que P205 é o peso ao desmame dos bezerros; PVP e PVD, os pesos das vacas ao parto e ao desmame, respectivamente; e NDTTOTAL, a exigência em energia para manutenção e produção de leite das vacas. As vacas Aberdeen Angus, com bezerros machos e aquelas com bezerros mestiços, foram mais eficientes. Vacas que utilizaram a pastagem cultivada por um período de tempo maior (T4 tiveram melhor desempenho do que aquelas que permaneceram apenas em pastagem natural(T1; as vacas dos outros tratamentos tiveram desempenhos intermediários.The objective of this work was to evaluate the productive efficiency of beef cows. Thirty Angus and 32 Charolais primiparous cows, pregnant at the beginning of the experiment with straightbred or crossbred calves, were evaluated. The cows were submitted to different feeding management during winter and spring: T1 -- Native pasture, T2 -- Cultivated pasture for 60 days (24 hours/day, from early September to early November, T3

  16. Change-management. From commercial power operation to post power operation and decommissioning; Change-Management. Vom Leistungsbetrieb ueber den Nachbetrieb zum Rueckbau. T. 1. Stilllegung und Rueckbau von Reaktoren und Anlagen im Brennstoffkreislauf durch AREVA

    Energy Technology Data Exchange (ETDEWEB)

    Wasinger, Karl [AREVA GmbH, Offenbach am Main (Germany)

    2015-02-15

    Transition from power generation to decommissioning challenges utilities. Power generation is mainly characterized by a stable working environment and constant workload, decommissioning and dismantling, however, by transformation and change. Also, changing requirements for the workforce's skills challenge the organization and its senior management. Ensuring effective and efficient performance, while maintaining motivation of staff, requires adjustment of management processes as well as of operational organization and human resources management. AREVA has more than 20 years of experience in decommissioning of own nuclear fuel cycle plants in France, as well as of other large plants and power reactors in Germany, the United Kingdom and the US. Therefore, the group has developed and successfully implemented integrated change management processes. The implementation of well-established and proven methods, developed by the productive industry and adjusted to the nuclear regulatory requirements, significantly improves the performance and efficiency of means and methods in use. The AREVA Performance Improvement Process defines concrete approaches to identify and improve potential deficits of productivity in six main areas (decommissioning scenarios and stra-tegies, waste treatment and logistics, operations management, supply chain, regulatory monitoring and controls as well as dismantling operation). Nuclear plant and facility owners around the world benefit from AREVA experts well experienced in execution of large and complex decommissioning projects.

  17. KONTEC 2013. 11{sup th} international symposium on 'Conditioning of radioactive operational and decommissioning waste' and 11{sup th} BMBF status report on 'Decommissioning and demolition of nuclear facilities'; KONTEC 2013. 11. internationales Symposium 'Konditionierung radioaktiver Betriebs- und Stilllegungsabfaelle' einschliesslich 11. Statusbericht des BMBF 'Stilllegung und Rueckbau kerntechnischer Anlagen'. Veranstaltungsbericht

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2013-06-15

    KONTEC 2013 was held in Dresden on 13 to 15 March 2013. The 11{sup th} event organized under this heading dealt with the subjects of 'Conditioning of Radioactive Operational and Decommissioning Waste' and 'Decommissioning and Demolition of Nuclear Facilities' including the R and D Status Report by the Federal Ministry of Education and Research (BMBF) on the same subject. The conference was attended by an international audience from 19 countries. The program included plenary sessions on these 4 key topics: - Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning. - Decommissioning and Dismantling of Nuclear Facilities. - Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes. - Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). These sessions were accompanied by poster sessions and short presentations under the heading of 'Kontec Direct.' The best presentations of the categories Plenary Session Presentation, Poster Presentation and Kontec-Direct have been awarded. In detail, 'Dismantling of Russian nuclear powered submarines' by Detlef Mietann, 'Requalification of 'Old Packages' for the Konrad Repository Described for the Model Case of Packages from Storage Annex A and Repackaging of Containers Holding Compacts in Hall 2 of the GNS Plant' by Martina Koessler, Sebastian Schwall and Pascal Budriks, and 'Electrochemical process development for cleaning organic, C-14-labelled waste solutions' by Hans-Juergen Friedrich. (orig.)

  18. THE DEACTIVATION DECONTAMINATION & DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT (PFP) A FORMER PLUTONIUM PROCESSING FACILITY AT DOE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    CHARBONEAU, S.L.

    2006-02-01

    The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington, DC and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (D&D) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP D&D effort includes descriptions of negotiations with the State of Washington concerning consent

  19. Regeneration of a confined aquifer after redevelopment and decommission of artesian wells, example from Grafendorf aquifer (Styria, Austria)

    Science.gov (United States)

    Mehmedovski, Nudzejma; Winkler, Gerfried

    2016-04-01

    Water is essential for life and it is therefore necessary to protect drinking water sustainably. Compared to shallow groundwater, deeper groundwater is especially important due to its characteristic tendency to remain extensively unaffected by environmental impacts. Thus, the uncontrolled waste of this valuable resource has to be avoided. A lot of artesian wells have been established in Grafendorf bei Hartberg (Styria, Austria). Almost all wells were not state-of-the art. As a result the different aquifer horizons began to intermix. Additionally some of the artesian wells had a permanent free overflow and the water was not even used. Consequently, since 1950, where the mean discharge of 37 wells was 0,334 l/s per well, the discharge has decreased to 0,090 l/s until 2013, which means a decline of about 75 %. As a reaction to these declines a decommissioning campaign was conducted where 69 artesian wells have been closed by injecting a cement-bentonite suspension (ratio 3:1). The Grafendorf aquifer is situated in the Styrian Basin and consists of 5 separated artesian horizons in Neogene sediments. These artesian horizons range from 42 m (1st horizon) to 176 m (5th horizon) and mostly consist of sand, partly of fine/medium/coarse gravel and partially with minor clay content. In order to analyse the reaction of the Grafendorf aquifer to these redevelopments, 5 monitoring wells could be used for the analysis. Some monitoring wells include different aquifer horizons and hydraulically short cut them. Thus, in this work the analysis focus on the general trend of the whole aquifer system neglecting the individual interactions between the different aquifers. In a first investigation step the hydraulic properties of the aquifer system has been determined using pumping tests which were analysed with different analytical solutions with the software AQTESOLV. Overall the pumping test solutions hardly differ in the transmissivity and hydraulic conductivity. On the contrary the

  20. The requirement for proper storage of nuclear and related decommissioning samples to safeguard accuracy of tritium data

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Daeji, E-mail: kimdj@kins.re.kr [Korea Institute of Nuclear Safety, 19 Guseong, Yuseong, Daejeon, 303-338 (Korea, Republic of); Croudace, Ian W.; Warwick, Phillip E. [GAU-Radioanalytical, University of Southampton, NOC, European Way, Southampton SO14 3ZH (United Kingdom)

    2012-04-30

    Highlights: Black-Right-Pointing-Pointer Identification of variation in tritium loss rates in concrete samples. Black-Right-Pointing-Pointer Quantification of variation in tritium loss rates under different storage conditions. Black-Right-Pointing-Pointer Quantification of tritium cross-contamination rates for a range of matrix types. Black-Right-Pointing-Pointer Storage strategies for routine waste characterisation involving tritium. - Abstract: Large volumes of potentially tritium-contaminated waste materials are generated during nuclear decommissioning that require accurate characterisation prior to final waste sentencing. The practice of initially determining a radionuclide waste fingerprint for materials from an operational area is often used to save time and money but tritium cannot be included because of its tendency to be chemically mobile. This mobility demands a specific measurement for tritium and also poses a challenge in terms of sampling, storage and reliable analysis. This study shows that the extent of any tritium redistribution during storage will depend on its form or speciation and the physical conditions of storage. Any weakly or moderately bound tritium (e.g. adsorbed water, waters of hydration or crystallisation) may be variably lost at temperatures over the range 100-300 Degree-Sign C whereas for more strongly bound tritium (e.g. chemically bound or held in mineral lattices) the liberation temperature can be delayed up to 800 Degree-Sign C. For tritium that is weakly held the emanation behaviour at different temperatures becomes particularly important. The degree of {sup 3}H loss and cross-contamination that can arise after sampling and before analysis can be reduced by appropriate storage. Storing samples in vapour tight containers at the point of sampling, the use of triple enclosures, segregating high activity samples and using a freezer all lead to good analytical practice.

  1. SMART 3D SUBSURFACE CONTAMINANT CHARACTERIZATION AT THE BGRR DECOMMISSIONING PROJECT. ACCELERATED SITE TECHNOLOGY DEPLOYMENT COST AND PERFORMANCE REPORT.

    Energy Technology Data Exchange (ETDEWEB)

    HEISER,J.; KALB,P.; SULLIVAN,T.; MILIAN,L.

    2001-12-01

    The BGRR was the world's first nuclear reactor dedicated to the peaceful exploration of atomic energy. The reactor pile consisted of a 700-ton, 25-foot cube of graphite fueled by uranium. A total of 1,369 fuel channels were available with roughly half in use at any given time. Insertion and removal of boron steel control rods controlled reactor power levels. One or more of five fans powered air-cooling. Air was brought in through two filtered plenums, flowed through and around the reactor core, through an exhaust duct containing filters, and finally out through the 320-foot high exhaust stack. Spent fuel was temporarily stored in the spent-fuel canal, and then sent to the Department of Energy's Savannah River Site (SRS). Access to the canal for removing spent fuel was through the Canal House (Building 709). The BGRR ceased operation in 1968 and was placed in a shutdown mode in which all fuel was removed and sent to SRS. Penetrations in the biological shield around the graphite cube and fuel channels were sealed. The final decontamination and decommissioning (D and D) process was initiated in 1999 and is scheduled for completion in 2005. An accelerated schedule was developed that combines characterization with removal actions for the various systems and structures. Before D and D work on a section of the BGRR facility begins, contaminant characterization is conducted to determine the types and amounts of contaminants present. The data are then used for project planning, including decisions affecting the extent of removal, waste designation, and health and safety plans.

  2. Assessment of radium-226 bioavailability and bioaccumulation downstream of decommissioned uranium operations, using the caged oligochaete (Lumbriculus variegatus).

    Science.gov (United States)

    Wiramanaden, Cheryl I E; Orr, Patricia L; Russel, Cynthia K

    2015-03-01

    The present study investigated the integrated effects of several geochemical processes that control radium-226 ((226) Ra) mobility in the aquatic environment and bioaccumulation in in situ caged benthic invertebrates. Radium-226 bioaccumulation from sediment and water was evaluated using caged oligochaetes (Lumbriculus variegatus) deployed for 10 d in 6 areas downstream of decommissioned uranium operations in Ontario and Saskatchewan, Canada. Measured (226) Ra radioactivity levels in the retrieved oligochaetes did not relate directly to water and sediment exposure levels. Other environmental factors that may influence (226) Ra bioavailability in sediment and water were investigated. The strongest mitigating influence on (226) Ra bioaccumulation factors was sediment barium concentration, with elevated barium (Ba) levels being related to use of barium chloride in effluent treatment for removing (226) Ra through barite formation. Observations from the present study also indicated that (226) Ra bioavailability was influenced by dissolved organic carbon in water, and by gypsum, carbonate minerals, and iron oxyhydroxides in sediment, suggestive of sorption processes. Environmental factors that appeared to increase (226) Ra bioaccumulation were the presence of other group (II) ions in water (likely competing for binding sites on organic carbon molecules), and the presence of K-feldspars in sediment, which likely act as a dynamic repository for (226) Ra where weak ion exchange can occur. In addition to influencing bioavailability to sediment biota, secondary minerals such as gypsum, carbonate minerals, and iron oxyhydroxides likely help mitigate (226) Ra release into overlying water after the dissolution of sedimentary barite. Environ Toxicol Chem 2015;34:507-517. © 2014 SETAC.

  3. Alternatives evaluation and decommissioning study on shielded transfer tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    DeVore, J.R.; Hinton, R.R.

    1994-08-01

    The shielded transfer tanks (STTs) are five obsolete cylindrical shipping casks which were used to transport high specific activity radioactive solutions by rail during the 1960s and early 1970s. The STTs are currently stored at the Oak Ridge National Laboratory under a shed roof. This report is an evaluation to determine the preferred alternative for the final disposition of the five STTs. The decommissioning alternatives assessed include: (1) the no action alternative to leave the STTs in their present location with continued surveillance and maintenance; (2) solidification of contents within the tanks and holding the STTs in long term retrievable storage; (3) sale of one or more of the used STTs to private industry for use at their treatment facility with the remaining STTs processed as in Alternative 4; and (4) removal of tank contents for de-watering/retrievable storage, limited decontamination to meet acceptance criteria, smelting the STTs to recycle the metal through the DOE contaminated scrap metal program, and returning the shielding lead to the ORNL lead recovery program because the smelting contractor cannot reprocess the lead. To completely evaluate the alternatives for the disposition of the STTs, the contents of the tanks must be characterized. Shielding and handling requirements, risk considerations, and waste acceptance criteria all require that the radioactive inventory and free liquids residual in the STTs be known. Because characterization of the STT contents in the field was not input into a computer model to predict the probable inventory and amount of free liquid. The four alternatives considered were subjected to a numerical scoring procedure. Alternative 4, smelting the STTs to recycle the metal after removal/de-watering of the tank contents, had the highest score and is, therefore, recommended as the preferred alternative. However, if a buyer for one or more STT could be found, it is recommended that Alternative 3 be reconsidered.

  4. Pilot-scale treatability testing -- Recycle, reuse, and disposal of materials from decontamination and decommissioning activities: Soda blasting demonstration

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    The US Department of Energy (DOE) is in the process of defining the nature and magnitude of decontamination and decommissioning (D and D) obligations at its sites. With disposal costs rising and available storage facilities decreasing, DOE is exploring and implementing new waste minimizing D and D techniques. Technology demonstrations are being conducted by LMES at a DOE gaseous diffusion processing plant, the K-25 Site, in Oak Ridge, Tennessee. The gaseous diffusion process employed at Oak Ridge separated uranium-235 from uranium ore for use in atomic weapons and commercial reactors. These activities contaminated concrete and other surfaces within the plant with uranium, technetium, and other constituents. The objective of current K-25 D and D research is to make available cost-effective and energy-efficient techniques to advance remediation and waste management methods at the K-25 Site and other DOE sites. To support this objective, O`Brien and Gere tested a decontamination system on K-25 Site concrete and steel surfaces contaminated with radioactive and hazardous waste. A scouring system has been developed that removes fixed hazardous and radioactive surface contamination and minimizes residual waste. This system utilizes an abrasive sodium bicarbonate medium that is projected at contaminated surfaces. It mechanically removes surface contamination while leaving the surface intact. Blasting residuals are captured and dissolved in water and treated using physical/chemical processes. Pilot-scale testing of this soda blasting system and bench and pilot-scale treatment of the generated residuals were conducted from December 1993 to September 1994.

  5. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include “clean” concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  6. Qualidade da carne do músculo longissimus dorsi de novilhos superjovens Aberdeen Angus de biótipo pequeno e médio abatidos com o mesmo estágio de acabamento na carcaça = Meat quality of the longissimus dorsi muscle of Aberdeen Angus steers of small and medium frame score, slaughtered at the same carcass finishing stage

    Directory of Open Access Journals (Sweden)

    Miguelangelo Ziegler Arboitte

    2011-04-01

    Full Text Available O objetivo deste trabalho foi verificar a influencia do biotipo pequeno e medio de novilhos Aberdeen Angus superjovens na composicao da carne do longissimus dorsi (LD. Foram utilizadas seccoes do LD de oito novilhos com biotipo pequeno e dez com biotipo medio, confinados por 158 dias, apresentando ao abate idade e peso vivo medio de 456 dias e 429 kg. A alimentacao foi constituida de silagem de sorgo e concentrado na relacao 60:40 nos primeiros 63 dias e apos 50:50 ate o abate. O biotipo foi calculado por meio da formula: B = -11,548 +(0,4878 x h - (0,0289 x ID + (0,0000146 x (ID2 + (0,0000759 x h x ID; h = altura em polegadas e ID=idade em dias. A carne do LD apresentou gordura intramuscular media (10,11 pontos; p = 0,7034, coloracao vermelha (4,33 pontos; p = 0,3724, textura com tendenciaa muito fina (4,61 pontos; p = 0,3075 e forca ao cisalhamento de 2,72 kgf cm-2 (p = 0,4009. A carne apresentou 72,27% (p = 0,4355 de umidade, 19,34% (p = 0,4150 de proteina bruta, 3,96% (p = 0,9071 de lipidios, 4,43% (p = 0,9842 de minerais e 0,25 mg 100g-1 de carne(p = 0,2375 de colesterol. Os biotipos nao influenciaram na concentracao dos acidos graxos palmitico (p = 0,0790, estearico (p = 0,2455, oleico (p = 0,3046, linoleico (p = 0,9456, ocorrendo alteracao na participacao do acido graxo miristico (. = 1,85 + 0,12B; p = 0,043. O estudo do biotipo na composicao da carne e importante para a identificacao de melhores caracteristicas nutraceuticas.The objective of this work was to assess the influence of small and medium frame scores in the meat composition of the longissimus dorsi (LD muscle of Abredeen Angus steers. We used LD sections from eight small-framed steers and ten medium-framed steers, confined for 158 days, with mean slaughter age of 457 days and 429 kg live weight. The feed was composed of sorghum silage and concentrate in a 60:40 ratio for the first 63 days, and 50:50 thereafter until slaughter. Frame wascalculated using the formula: F=-11

  7. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle; Determinacion de Uranio en Muestras Procedentes del Desmantelamiento de Instalaciones de la Primera Parte del Cielo del Combustible Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A.; Correa, E.; Navarro, N.; Sancho, C. [Ciemat, Madrid (Spain); Angeles, A.

    2000-07-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  8. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A. J. [comp.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately.

  9. ''Rueckbau 2014''. KWS Congress regarding decommissioning and dismantling at Zwentendorf nuclear training power plant; ''Rueckbau 2014''. KWS-Rueckbau-Fachtagung im Schulungskernkraftwerk Zwentendorf

    Energy Technology Data Exchange (ETDEWEB)

    Maassen, Herbert [KRAFTWERKSSCHULE E.V. (KWS), Essen (Germany)

    2015-06-01

    From September 24 to 25, 2014, KRAFTWERKS-SCHULE E.V. (KWS) held the congress ''Rueckbau 2014''.This first congress about nuclear power plant decommissioning was combined with an exhibition in the fully equipped Zwentendorf nuclear training power plant. The exhibitors had the opportunity to present and test their products in the ambience of a real nuclear power plant, close to original plant components. The visitors got a general overview of the on-site conditions. During the lectures the process of decommissioning and dismantling of a nuclear power plant were described, problems within this process were discussed, and possible solutions were recommended.

  10. Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 3: Technology evaluation data sheets; Part A: Characterization, dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. The TLD uses information from the Strategic Roadmap for the Oak Ridge Reservation, the Oak Ridge K-25 Site Technology Logic Diagram, the Oak Ridge National Laboratory Technology Logic Diagram, and a previous Hanford logic diagram. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. This report consists of the characterization and dismantlement data sheets.

  11. Decommissioning of the Nuclear Reactors R2 and R2-0 at Studsvik, Sweden. General Data as called for under Article 37 of the Euratom Treaty

    Energy Technology Data Exchange (ETDEWEB)

    2009-01-15

    This document describes the plans for decommissioning of the nuclear research and material test reactors R2 and R2-0, situated at the Studsvik site close to the city of Nykoeping, Sweden. The purpose of the document is to serve as information for the European Commission, and to fulfil the requirements of Article 37 of the Euratom Treaty. Studsvik is situated on the Baltic coast, about 20 km east of Nykoeping and 80 km southwest of Stockholm. The site comprises the reactors R2 and R2-0 and several facilities for material investigation and radioactive waste treatment and storage. The reactors were used for a number of different purposes from 1960 until June 2005, when they were shut down following a decision by the operator. Decommissioning of the reactor facility is planned to be completed in 2016 after dismantling and conditioning of radioactive parts and demolition of the facility. Solid and liquid radioactive wastes from the dismantling activities will be treated and stored on-site awaiting final disposal. The waste treatment facilities, which are situated in other buildings at the Studsvik site, are planned to continue operation during and after the decommissioning of the reactor facility. All nuclear fuel has been transferred to a separate storage facility and is being shipped to the US according to existing agreements. The objective of the planned dismantling activities is to achieve clearance of the facility to make it possible to either demolish the buildings or use them for other purposes. The operator has divided the planning for dismantling and demolition of the facility into three phases [1]: Dismantling 1, including primary system decontamination, dismantling of the reactors with systems in the reactor pool, draining, cleaning and temporary covering of the reactor pool. This phase has begun and is due to last till approximately December 2009. Dismantling 2, including dismantling of systems in the reactor facility, removal of equipment, radiological

  12. PARTICULARITIES REGARDING THE OPERATING PROCESS OF THE CUTTING AND EXTRACTION DEVICE IN THE CANDU HORIZONTAL FUEL CHANNELS PRESSURE TUBE DECOMMISSIONING PART II: CUTTING AND EXTRACTING PRESSURE TUBE PROCESS

    Directory of Open Access Journals (Sweden)

    Constantin POPESCU

    2016-05-01

    Full Text Available This paper presents some details of operation process for a Cutting and Extraction Device (CED in order to achieve the decommissioning of the horizontal fuel channels pressure tube in the CANDU 6 nuclear reactor. The most important characteristic of the Cutting and Extraction Device (CED is his capability of totally operator’s protection against the nuclear radiation during pressure tube decommissioning. The cutting and extracting pressure tube processes present few particularities due to special adopted technical solutions: a special module with three cutting rollers (system driven by an actuator, a guiding-extracting and connecting module (three fixing claws which are piloted by an actuator and block the device in the connecting position with extracting plugs. The Cutting and Extraction Device (CED is a train of modules equipped with special systems to be fully automated, connected with a Programmable Logic Controller (PLC and controlled by an operator panel type Human Machine Interface (HMI. All processes are monitored by video cameras. In case of error, the process is automatically stopped, the operator receiving an error message and the last sequence could be reinitialized or aborted due to safety reasons.

  13. 2016 Inspection and Annual Site Status Report for the Site A/Plot M, Illinois, Decommissioned Reactor Site July 2016

    Energy Technology Data Exchange (ETDEWEB)

    Murl, Jeffrey [USDOE Office of Legacy Management, Washington, DC (United States); Miller, Michele [Navarro Research and Engineering, Oak Ridge, TN (United States)

    2016-07-01

    The Site A/Plot M, Illinois, Decommissioned Reactor Site was inspected on May 17, 2016. The site, located within Cook County forest preserve that is open to the public, was found to be in good condition with one exception. Erosion on top of the grass-covered mound at Plot M continues to be a concern as presented in previous inspections. Ruts form in the soil on top of Plot M as a result of bike traffic using the open field as a pass thru between established bike trails within the forest preserve. Argonne National Laboratory (ANL) who is contracted directly from U.S. Department of Energy (DOE) has filled in the ruts with top soil and reseeding remains an ongoing process. Reseeded areas from 2015 are progressing nicely. No cause for a follow-up inspection was identified. In 2015, ANL plugged and abandoned 8 of 25 monitoring wells (BH41, BH51, BH52, BH54, DH9, DH10, DH13, and DH17). The 17 groundwater monitoring wells remaining at the site were inspected to confirm that they were locked and in good condition. Preliminary environmental monitoring results for 2015 are provided in a draft report titled Surveillance of Site A and Plot M, Report for 2015, prepared by ANL. The report also contains results of an independent analysis conducted by the Illinois Emergency Management Agency on some of the samples collected by ANL in 2015. The draft report states that the results of the surveillance program continue to indicate that the impact of radioactivity at Site A/Plot M is very low and does not endanger the health of those living in the area or visiting the site. The ANL monitoring report will be made available to the public on the DOE Office of Legacy Management public website when it is issued as final. A new county forest preserve campsite opened in 2015 at Bull Frog Lake, which is east of Plot M. Hiking trails connect Bull Frog Lake with Site A/Plot M. The site might receive more traffic from forest preserve visitors now that this new campsite is opened.

  14. ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING DEACTIVATION AND DECOMMISSIONING OF REACTOR VESSELS AT THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Wiersma, B.; Serrato, M.; Langton, C.

    2010-11-10

    The R- and P-reactor vessels at the Savannah River Site (SRS) are being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of physically isolating and stabilizing the reactor vessel by filling it with a grout material. The reactor vessels contain aluminum alloy materials, which pose a concern in that aluminum corrodes rapidly when it comes in contact with the alkaline grout. A product of the corrosion reaction is hydrogen gas and therefore potential flammability issues were assessed. A model was developed to calculate the hydrogen generation rate as the reactor is being filled with the grout material. Three options existed for the type of grout material for D&D of the reactor vessels. The grout formulation options included ceramicrete (pH 6-8), a calcium aluminate sulfate (CAS) based cement (pH 10), or Portland cement grout (pH 12.4). Corrosion data for aluminum in concrete were utilized as input for the model. The calculations considered such factors as the surface area of the aluminum components, the open cross-sectional area of the reactor vessel, the rate at which the grout is added to the reactor vessel, and temperature. Given the hydrogen generation rate, the hydrogen concentration in the vapor space of the reactor vessel above the grout was calculated. This concentration was compared to the lower flammability limit for hydrogen. The assessment concluded that either ceramicrete or the CAS grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters did not provide a margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. Therefore, it was recommended that this grout not be utilized for this task. On the other hand, the R-reactor vessel

  15. An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    Energy Technology Data Exchange (ETDEWEB)

    Kristofova, Kristina; Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2007-01-15

    The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA.

  16. FLUOR HANFORD DECOMMISSIONING UPDATE

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2008-04-21

    Fluor Hanford is completing D&D of the K East Basin at the U.S. Department of Energy's (DOE's) Hanford Site in southeastern Washington State this spring, with demolition expected to begin in June. Located about 400 yards from the Columbia River, the K East Basin is one of two indoor pools that formerly contained irradiated nuclear fuel, radioactive sludge and tons of contaminated debris. In unique and path-breaking work, workers finished removing the spent fuel from the K Basins in 2004. In May 2007, workers completed vacuuming the sludge into containers in the K East Basin, and transferring it into containers in the K West Basin. In December, they finished vacuuming the remainder of K West Basin sludge into these containers. The K East Basin was emptied of its radioactive inventory first because it was more contaminated than the K West Basin, and had leaked in the past. In October 2007, Fluor Hanford began physical D&D of the 8,400-square foot K East Basin by pouring approximately 14-inches of grout into the bottom of it. Grout is a type of special cement used for encasing waste. Two months later, Fluor Hanford workers completed sluicing contaminated sand from the large filter that had sieved contaminants from the basin water for more than 50 years. Next, they poured grout into the filter housing and the vault that surrounds the filter, as well as into ion exchange columns that also helped filter basin water. For a six-week period in February and March, personnel drained the approximately one million gallons of contaminated water from the K East Basin. The effort required more than 200 tanker truck loads that transported the water to an effluent treatment facility for treatment and then release. A thin fixative was also applied to the basin walls as the water was removed to hold residual contamination in place. As soon as the water was out of the basin, Fluor pumped in approximately 18 feet of 'controlled density fill' material (somewhat similar to sand) to shield workers to a safe level from the residual radioactivity. Workers then continued preparations for demolishing the structure. Currently, they are isolating utilities, removing asbestos, draining oils, and removing other items not allowed to be disposed in Hanford's Environmental Restoration Disposal Facility (ERDF). The basin's superstructure will be demolished using a heavy industrial excavator equipped with a shear. This portion of the work is expected to be completed in September, with removal of the basin substructure to follow in 2009. D&D of the K East Basin eliminated the final major radioactive sources there, and made the Columbia River and the adjacent environment safer for everyone who lives downstream.

  17. Environmental assessment after decommissioning at the North Sea- Froey oil production site: a field study with biomarkers in fish and invertebrates

    Energy Technology Data Exchange (ETDEWEB)

    Pinturier, Laurence; Beyer, Jonny; Moltu, Ulf; Plisson, Saune Stephan; Berland, Harald; Sundt, Rolf; Bjoernstad, Anne; Sanni, Steinar

    2006-03-15

    The Froey field is situated in the North Sea and was operated by Total Exploration and Production Norge. Oil production started in 1995 and ceased in 2001, when the wells were permanently plugged and abandoned. The jacket was removed in 2002, and in 2003 the first post-production sediment monitoring survey was carried out at the field as a part of the regional sediment environmental monitoring survey of Region II. In parallel to the sediment monitoring survey and cuttings survey, Total E and P Norge decided to conduct an environmental survey based on the use of biological effects parameters (or biomarkers) to document the environmental condition of the site after decommissioning. A series of pollutant responsive biomarkers was selected in order to answer the following questions: is the environmental condition in the bottom water at the Froey location significantly different to the background situation as measured in the reference station? And does the cutting deposit affect the nearby environment. Conclusion: This paper present a selection of the results obtained during an environmental survey carried out at a decommissioned field, the Froey field, by Total E and P Norge and RF-Akvamiljoe. Detailed results and discussion will be presented more extensively in a peer review publication by Beyer et al. (2005). The objective of the survey was to evaluate the environmental condition at the Froey site by comparing it to a background situation measured at a reference site. The environmental condition was assessed by measuring biological effects parameters in invertebrates and fish living in close connection with the sediments. The results of this survey indicate only a very local pollutant effect in the vicinity of the cuttings limited to the invertebrates living and feeding on the sediment. No signal effects were measured in the selected fish species known to swallow large quantity of sediment when feeding. These results corroborate well the ones obtained from the

  18. Safety Evaluation Report for the Tennessee Valley Authority's Plan to Decommission its Low-Level Radioactive Waste Burial Site at Muscle Shoals, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    Gant, K.S.; Kettelle, R.H.

    1998-11-01

    From 1966 to 1981, the Tennessee Valley Authority (TVA) operated a burial site, licensed under the former 10 CFR 20.304, for low-level radioactive waste on its Muscle Shoals, Alabama, reservation. TVA submitted a decommissioning plan for the burial site and requested approval for unrestricted use of the site. The Nuclear Regulatory Commission requested Oak Ridge National Laboratory (ORNL) to evaluate this plan to determine if the site meets the radiological requirements for unrestricted use as specified in 10 CFR 20.1402; that is, an average member of the critical group would not receive more than 25 mrem/y from residual radioactivity at the TVA Low-Level Radioactive Waste Burial Site and the radioactivity has been reduced to levels as low as reasonably achievable (ALARA).

  19. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    Energy Technology Data Exchange (ETDEWEB)

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States); Donohoue, Tom; Martin, E. Ray; Mason, John A. [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States); Norton, Christopher J.; Crosby, Daniel [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States); Nachtman, Thomas J. [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)

    2013-07-01

    This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

  20. US Department of Energy Grand Junction Projects Office Remedial Action Project, final report of the decontamination and decommissioning of Building 36 at the Grand Junction Projects Office Facility

    Energy Technology Data Exchange (ETDEWEB)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 36 was found to be radiologically contaminated and was demolished in 1996. The soil beneath the building was rem