Very Low Level Radioactive Solid Waste Management in CHINA

Energy Technology Data Exchange (ETDEWEB)

Li, Ting Jun [No. 117 Xisanhuanbeilu, Haidian District, Beijing (China)

2011-06-15

This paper introduces the policy and regulations on very low level waste (VLLW) management in China. Given the important decommissioning and site restoration program of the old facility, it is considered necessary to create a new disposal facility dedicated to VLLW. Many general design principles are in common with to the disposal facility for low and intermediate level waste (LILW), namely the isolation of the waste by means of a multibarrier system, but using bentonite and/or high density polyethylene membranes instead of the generalized use of concrete barriers. The design of the facility is consistent with the design of disposal facilities for hazardous waste. The engineering design of two VLLW disposal facilities is introduced.

Consignment of Very Low Level Waste (VLLW) from the Winfrith dragon reactor containment building

International Nuclear Information System (INIS)

Shuler, K.

2008-01-01

The United Kingdom Atomic Energy Authority (UKAEA), CH2M Hill and AMEC are implementing innovative technical approaches in the decommissioning of redundant nuclear plant. These approaches will form the basis of lessons learned and best practices to be applied to future decommissioning work across the United Kingdom. This paper highlights the approach used for categorizing waste from the Dragon Decommissioning Project as Very Low Level Waste (VLLW), a category typically used by hospitals and laboratories for small quantities of waste contaminated with radioisotopes. (authors)

Characteristics study of bentonite as candidate of buffer materials for radioactive waste disposal system

International Nuclear Information System (INIS)

Suryantoro; Arimuladi, S.P.; Sastrowardoyo, P.B.

1998-01-01

Literature studies on bentonite characteristic of, as candidate for radioactive waste disposal system, have been conducted. Several information have been obtained from references, which would be contributed on performance assessment of engineered barrier. The functions bentonite includes the buffering of chemical and physical behavior, i.e. swelling property, self sealing, hydraulic conductivities and gas permeability. This paper also presented long-term stability of bentonite in natural condition related to the illitisazation, which could change its buffering capacities. These information, showed that bentonite was satisfied to be used for candidate of buffer materials in radioactive waste disposal system. (author)

Preliminary safety concept for disposal of the very low level radioactive waste in Romania.

Science.gov (United States)

Niculae, O; Andrei, V; Ionita, G; Duliu, O G

2009-05-01

In Romania, there are certain nuclear installations in operation or under decommissioning, all of them representing an important source of very low level waste (VLLW). This paper presents an overview on the approach of the VLLW management in Romania, focused on those resulted from the nuclear power plants decommissioning. At the same time, the basic elements of safety concept, together with some safety evaluations concerning VLLW repository are presented and discussed too.

INPP Landfill[Disposal of very low level radioactive waste at Ignalina NPP

Energy Technology Data Exchange (ETDEWEB)

Dahlberg, Jan; Bergstroem, Ulla

2004-06-15

The objective of this report is to propose the basic design for final disposal of Very Low Level Radioactive Waste (VLLW) produced at the Ignalina Nuclear Power Plant and at other small waste producers in Lithuania. Considering the safety for the environment, as well as the construction costs, it has been decided that the repository will be of a landfill type based on the same design principles as similar authorised facilities in other countries. It has also been decided that the location of the landfill shall be in the vicinity of the Ignalina Nuclear Power Plant (INPP)

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

Science.gov (United States)

Nancarrow, D J; White, M M

2004-03-01

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land

International Nuclear Information System (INIS)

Nancarrow, D J; White, M M

2004-01-01

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950 000 m 3 ). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

An investigation report on the status of very low level radioactive waste management in China

International Nuclear Information System (INIS)

Sun Donghui

2008-01-01

This report briefly introduces the result of investigation on the study of Very Low Level Waste (VLLW) management and the engineering details of landfill facilities for slightly contaminated waste produced during past few decades in China. Since it has been recognized by IAEA and some countries, that VLLW can be disposed in the landfill for hazardous waste, industrial waste or garbage from cities, standards involved with the non-radioactive solid waste disposal were collected and the brief information in situ for some landfill projects, just like in Beijing and Shanghai, are also given in this report. In the end, some questions and points of view are raised, on which I wish to discuss with you. These points could be very important, when we want to develop the standard for VLLW management. (authors)

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Bullen, D.B.; Gdowski, G.E.; Weiss, H.

1988-06-01

Three copper-based alloys, CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni), are being considered along with three austenitic candidates as possible materials for fabrication of containers for disposal of high-level radioactive waste. The waste will include spent fuel assemblies from reactors as well as high-level reprocessing wastes in borosilicate glass and will be sent to the prospective repository at Yucca Mountain, Nevada, for disposal. The containers must maintain mechanical integrity for 50 yr after emplacement to allow for retrieval of waste during the preclosure phase of repository operation. Containment is required to be substantially complete for up to 300 to 1000 yr. During the early period, the containers will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. The final closure joint will be critical to the integrity of the containers. This volume surveys the available data on the metallurgy of the copper-based candidate alloys and the welding techniques employed to join these materials. The focus of this volume is on the methods applicable to remote-handling procedures in a hot-cell environment with limited possibility of postweld heat treatment. The three copper-based candidates are ranked on the basis of the various closure techniques. On the basis of considerations regarding welding, the following ranking is proposed for the copper-based alloys: CDA 715 (best) > CDA 102 > CDA 613 (worst). 49 refs., 15 figs., 1 tab

Study of classification and disposed method for disused sealed radioactive source in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk Hoon; Kim, Ju Youl; Lee, Seung Hee [FNC Technology Co., Ltd.,Yongin (Korea, Republic of)

2016-09-15

In accordance with the classification system of radioactive waste in Korea, all the disused sealed radioactive sources (DSRSs) fall under the category of EW, VLLW or LILW, and should be managed in compliance with the restrictions for the disposal method. In this study, the management and disposal method are drawn in consideration of half-life of radionuclides contained in the source and A/D value (i.e. the activity A of the source dividing by the D value for the relevant radionuclide, which is used to provide an initial ranking of relative risk for sources) in addition to the domestic classification scheme and disposal method, based on the characteristic analysis and review results of the management practices in IAEA and foreign countries. For all the DSRSs that are being stored (as of March 2015) in the centralized temporary disposal facility for radioisotope wastes, applicability of the derivation result is confirmed through performing the characteristic analysis and case studies for assessing quantity and volume of DSRSs to be managed by each method. However, the methodology derived from this study is not applicable to the following sources; i) DSRSs without information on the radioactivity, ii) DSRSs that are not possible to calculate the specific activity and/or the source-specific A/D value. Accordingly, it is essential to identify the inherent characteristics for each of DSRSs prior to implementation of this management and disposal method.

Assessment of candidate sites for disposal of treated effluents at the Hanford Site, Washington

International Nuclear Information System (INIS)

Davis, J.D.

1992-01-01

A rigidly defined evaluation process was used to recommend a preferred location to dispose of treated effluents from facilities in the 200 Areas of the US Department of Energy's Hanford Site in Washington State. First, siting constraints were defined based on functional design considerations and siting guidelines. Then, criteria for selecting a preferred site from among several candidates were identified and their relative importance defined. Finally, the weighted criteria were applied and a site was selected for detailed characterization by subsurface investigations

Regulatory supervision of industrial waste containing very low activities of man-made radionuclides at SevRAO facility

International Nuclear Information System (INIS)

Sneve, Malgorzata K.; Kochetkov, Oleg; Monastyrskaya, Svetlana; Barchukov, Valerie; Romanov, Vladimir

2008-01-01

Full text: Large amounts of waste and materials with very low activity level are generated during operation and especially during decommissioning of nuclear facilities. Selection of the optimum economic and ecologically safe management option of such material is complicated by its specific features: very low level radiation exposure to individuals but rather large initial amounts of waste. On the one hand, it is a poor use of limited resources to em place such low activity waste into expensive facilities for radioactive waste storage and disposal if the radiological impact would be very small even for a much less expensive option; on the other hand, there is some apprehension regarding safety both about its disposal to landfills for conventional (non-radioactive) waste disposal, and about its limited or unlimited re-use or re-cycling. To regulate such waste management, a special waste category is introduced - very low level waste (VLLW). This category includes waste containing radionuclides with specific activity levels, which are higher than clearance levels, but do not need high containment and isolation. This paper discusses experience of regulatory development for VLLW control during remediation of radiation hazardous facilities in northwest Russia. The work has promoted identification of some challenges, whose solution has affected the waste management strategy at the sites. One of the main problems resolved was the selection of criteria according to which waste is allocated to the VLLW category. These is turn were partly determined by the radiological criteria chosen for protection of the public during this waste disposal. Elaboration of safe VLLW management strategy depends upon a source of waste generation and of its radiological composition. The VLLW management strategy at an operating enterprise, e.g. a nuclear power plant is rather different from the strategy implemented at the plant under decommissioning, or at storage facilities for the legacy waste

German approach to VLLW management

International Nuclear Information System (INIS)

Broecking, D.

1997-01-01

Waste generated in German nuclear facilities is exhaustively and selectively manage through a system adapted to the waste's characteristics. The management of the waste ensures that the impact on the workers, population and the environment is acceptable. This is done through a detailed documentation and quality assurance program which applies not only to radioactive waste but also to cleanable material used within a licensed practice. In Germany the producer is responsible for the waste generated in a licensed facility and is therefore responsible for the correct disposal, which depends on the waste's characteristics. Since the waste producer requires a license for all activities involving radioactive substances, the atomic authority is continuously informed and can therefore monitor the producer for compliance with the regulations. The use and disposal of all material in a licensed practice is documented and can therefore be traced by the authorities. Clearance is seen in Germany as the best way of managing non-radioactive material in a licensed practice. Germany has developed clearance procedures which guarantee that after clearance the radiological impact is negligible. (author)

Selection of candidate sites for a LLRW disposal facility in Connecticut

International Nuclear Information System (INIS)

Gingerich, Ronald E.; Holeman, George R.; Hileman, James A.

1992-01-01

Connecticut, one of the two members of the Northeast Interstate Low-Level Radioactive Waste Management Compact, has been directed by the Compact Commission to site a facility to manage the low-level radioactive waste (LLRW) generated in Connecticut. The Connecticut Hazardous Waste Management Service (CHWMS) has been given the responsibility to identify a site in the state for a LLRW disposal facility. The CHWMS has decided to plan for a site with an operating life of 50 years. A site of at least 160 acres will be needed to accommodate (he expected volume of LLRW and meet state and federal site requirements. A Site Selection Plan establishing the process and criteria to be used in siting a facility was adopted by the CHWMS in November 1990. The Plan calls for a stepwise screening of the state using published data to identify three candidate sites. A preferred site will be selected from among the candidate sites using onsite testing. The site selection criteria, which closely follow state and federal statutory and regulatory requirements, are divided into three types: exclusionary, avoidance and preference. Battelle Memorial Institute was selected as the contractor to assist the CHWMS in site screening. With guidance from the CHWMS, Battelle undertook screening of the state by applying the exclusionary, avoidance and preference criteria in three steps to identify from eight to twelve potential sites. The CHWMS Board of Directors bad decided that it wanted to be closely involved in the selection of the three candidate sites and to do so in a way that precluded the political and parochial pressures that are inevitably associated with a siting process. To meet these two goals a geographically neutral approach was devised for candidate site selection. In June, 1991 the CHWMS, with assistance from Battelle, conducted a three day workshop, open to the public, in which eight sites were presented to the Board. Data on the sites were presented in a way that did not disclose

Regional hydrogeological conceptual model of candidate Beishan area for high level radioactive waste disposal repository

International Nuclear Information System (INIS)

Wang Hailong; Guo Yonghai

2014-01-01

The numerical modeling of groundwater flow is an important aspect of hydrogeological assessment in siting of a high level radioactive waste disposal repository. Hydrogeological conceptual model is the basic and premise of numerical modeling of groundwater flow. Based on the hydrogeological analysis of candidate Beishan area, surface water system was created by using DEM data and the modeling area is determined. Three-dimensional hydrogeological structure model was created through GMS software. On the basis of analysis and description of boundary condition, flow field, groundwater budget and hydrogeological parameters, hydrogeological conceptual model was set up for the Beishan area. (authors)

The future supply of and demand for candidate materials for the fabrication of nuclear fuel waste disposal containers

International Nuclear Information System (INIS)

Grover, L.K.

1990-01-01

This report summarizes the findings of a literature survey carried out to assess the future world supply of and demand for titanium, copper and lead. These metals are candidate materials for the fabrication of containers for the immobilization and disposal of Canada's nuclear used-fuel waste for a reference Used-fuel Disposal Centre. Such a facility may begin operation by approximately 2020, and continue for about 40 years. The survey shows that the world has abundant supplies of titanium minerals (mostly in the form of ilmenite), which are expected to last up to at least 2110. However, for copper and lead the balance between supply and demand may warrant increased monitoring beyond the year 2000. A number of factors that can influence future supply and demand are discussed in the report

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Farmer, J.C.; McCright, R.D.; Kass, J.N.

1988-06-01

Three iron- to nickel-based austenitic alloys and three copper-based alloys are being considered as candidate materials for the fabrication of high-level radioactive-waste disposal containers. The austenitic alloys are Types 304L and 316L stainless steels and the high-nickel material Alloy 825. The copper-based alloys are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). Waste in the forms of both spent fuel assemblies from reactors and borosilicate glass will be sent to the prospective repository at Yucca Mountain, Nevada. The decay of radionuclides will result in the generation of substantial heat and gamma radiation. Container materials may undergo any of several modes of degradation in this environment, including undesirable phase transformations due to a lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking; and transgranular stress corrosion cracking. Problems specific to welds, such as hot cracking, may also occur. A survey of the literature has been prepared as part of the process of selecting, from among the candidates, a material that is adequate for repository conditions. The modes of degradation are discussed in detail in the survey to determine which apply to the candidate alloys and the extent to which they may actually occur. The eight volumes of the survey are summarized in Sections 1 through 8 of this overview. The conclusions drawn from the survey are also given in this overview

Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

International Nuclear Information System (INIS)

Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

1997-01-01

Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Bullen, D.B.; Gdowski, G.E.

1988-08-01

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of high-level radioactive-waste disposal containers. The waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The copper-based alloy materials are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The austenitic materials are Types 304L and 316L stainless steels and Alloy 825. The waste-package containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr, and they must be retrievable from the disposal site during the first 50 yr after emplacement. The containers will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. This volume surveys the available data on the phase stability of both groups of candidate alloys. The austenitic alloys are reviewed in terms of the physical metallurgy of the iron-chromium-nickel system, martensite transformations, carbide formation, and intermetallic-phase precipitation. The copper-based alloys are reviewed in terms of their phase equilibria and the possibility of precipitation of the minor alloying constituents. For the austenitic materials, the ranking based on phase stability is: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is: CDA 102 (oxygen-free copper) (best), and then both CDA 715 and CDA 613. 75 refs., 24 figs., 6 tabs

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Gdowski, G.E.; Bullen, D.B.

1988-08-01

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of containers for disposal of high-level radioactive waste. This waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, they must be retrievable from the disposal site. Shortly after the containers are emplaced in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of the high-level waste. This volume surveys the available data on oxidation and corrosion of the iron- to nickel-based austenitic materials (Types 304L and 316L stainless steels and Alloy 825) and the copper-based alloy materials [CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni)], which are the present candidates for fabrication of the containers. Studies that provided a large amount of data are highlighted, and those areas in which little data exists are identified. Examples of successful applications of these materials are given. On the basis of resistance to oxidation and general corrosion, the austenitic materials are ranked as follows: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is as follows: CDA 715 and CDA 613 (both best), and CDA 102 (worst). 110 refs., 30 figs., 13 tabs

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Energy Technology Data Exchange (ETDEWEB)

Gdowski, G.E.; Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of containers for disposal of high-level radioactive waste. This waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, they must be retrievable from the disposal site. Shortly after the containers are emplaced in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of the high-level waste. This volume surveys the available data on oxidation and corrosion of the iron- to nickel-based austenitic materials (Types 304L and 316L stainless steels and Alloy 825) and the copper-based alloy materials (CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni)), which are the present candidates for fabrication of the containers. Studies that provided a large amount of data are highlighted, and those areas in which little data exists are identified. Examples of successful applications of these materials are given. On the basis of resistance to oxidation and general corrosion, the austenitic materials are ranked as follows: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is as follows: CDA 715 and CDA 613 (both best), and CDA 102 (worst). 110 refs., 30 figs., 13 tabs.

Prospective implementation of a software application for pre-disposal L/ILW waste management activities in Romania

International Nuclear Information System (INIS)

Fako, Raluca; Sociu, Florin; Stan, Camelia; Georgescu, Roxana; Barariu, Gheorghe

2013-01-01

Romania is actively engaged to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Considering relevant documents to be further updated, about 122,000 m 3 SL-LILW are to be disposed in a near surface facility that will have room, also, for quantities of VLLW. Planned date for commissioning is under revision. Taking into account that in this moment there are initiated several actions for the improvement of the technical capability for LILW treatment and conditioning, several steps for the possible use of SAFRAN software were considered. In view of specific data for Romanian radioactive waste inventory, authors are trying to highlight the expected limitations and unknown data related with the implementation of SAFRAN software for the foreseen pre-disposal waste management activities. There are challenges that have to be faced in the near future related with clear definition of the properties of each room, area and waste management activity. This work has the aim to address several LILW management issues in accordance with national and international regulatory framework for the assurance of nuclear safety. Also, authors intend to develop their institutional capability for the safety demonstration of the existent and future radioactive waste management facilities and activities. (authors)

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Farmer, J.C.; Van Konynenburg, R.A.; McCright, R.D.; Gdowski, G.E.

1988-06-01

Three copper-based alloys, CDA 102 (oxygen-free, high-purity copper), CDA 613 (aluminum bronze), and CDA 715 (Cu-30Ni), are candidates for the fabrication of high-level radioactive-waste disposal containers. Waste will include spent fuel assemblies from reactors as well as borosilicate glass, and will be sent to the prospective repository site at Yucca Mountain in Nye County, Nevada. The decay of radionuclides will result in the generation of substantial heat and in fluxes of gamma radiation outside the containers. In this environment, container materials might degrade by atmospheric oxidation, general aqueous phase corrosion, localized corrosion (LC), and stress corrosion cracking (SCC). This volume is a critical survey of available data on pitting and crevice corrosion of the copper-based candidates. Pitting and crevice corrosion are two of the most common forms of LC of these materials. Data on the SCC of these alloys is surveyed in Volume 4. Pitting usually occurs in water that contains low concentrations of bicarbonate and chloride anions, such as water from Well J-13 at the Nevada Test Site. Consequently, this mode of degradation might occur in the repository environment. Though few quantitative data on LC were found, a tentative ranking based on pitting corrosion, local dealloying, crevice corrosion, and biofouling is presented. CDA 102 performs well in the categories of pitting corrosion, local dealloying, and biofouling, but susceptibility to crevice corrosion diminishes its attractiveness as a candidate. The cupronickel alloy, CDA 715, probably has the best overall resistance to such localized forms of attack. 123 refs., 11 figs., 3 tabs

The characterization and testing of candidate immobilization forms for the disposal of plutonium

International Nuclear Information System (INIS)

Bakel, A. J.; Buck, E. C.; Chamberlain, D. B.; Ebbinghaus, B. B.; Fortner, J. A.; Marra, J. C.; Mcgrail, B. P.; Mertz, C. J.; Peeler, D. K.; Shaw, H. F.; Strachan, D. M.; Van Konynenburg, R. A.; Vienna, J. D.; Wolf, S. F.

1997-01-01

Candidate immobilization forms for the disposal of surplus weapons-useable are being tested and characterized. The goal of the testing program was to provide sufficient data that, by August 1997, an informed selection of a single immobilization form could be made so that the form development and production R and D could be more narrowly focused. Two forms have been under consideration for the past two years: glass and ceramic. In August, 1997, the Department of Energy (DOE) selected ceramic for plutonium disposition, halting further work on the glass material. In this paper, we will briefly describe these two waste forms, then describe our characterization techniques and testing methods. The analytical methods used to characterize altered and unaltered samples are the same. A full suite of microscopic techniques is used. Techniques used include optical, scanning electron, and transmission electron microscopies. For both candidate immobilization forms, the analyses are used to characterize the material for the presence of crystalline phases and amorphous material. Crystalline materials, either in the untested immobilization form or in the alteration products from testing, are characterized with respect to morphology, crystal structure, and composition. The goal of these analyses is to provide data on critical issues such as Pu and neutron absorber volubility in the immobilization form, thermal stability, potential separation of absorber and Pu, and the long-term behavior of the materials. Results from these analyses will be discussed in the presentation. Testing methods include MCC-1 tests, product consistency tests (methods A and B), unsaturated ''drip'' tests, vapor hydration tests, single-pass flow-through tests, and pressurized unsaturated flow tests. Both candidate immobilization forms have very low dissolution rates; examples of typical test results will be reported

Factors influencing U(VI adsorption onto soil from a candidate very low level radioactive waste disposal site in China

Directory of Open Access Journals (Sweden)

Zuo Rui

2016-01-01

Full Text Available The properties of soil at disposal sites are very important for geological disposal of very low level radioactive waste in terms of U(VI. In this study, soil from a candidate very low level radioactive waste disposal site in China was evaluated for its capacity on uranium sorption. Specifically, the equilibrium time, initial concentration, soil particle, pH, temperature, and carbonate were evaluated. The results indicated that after 15-20 days of sorption, the Kd value fluctuated and stabilized at 355-360 mL/g. The adsorptive capacity of uranium was increased as the initial uranium concentration increased, while it decreased as the soil particle size increased. The pH value played an important role in the U(VI sorption onto soil, especially under alkaline conditions, and had a great effect on the sorption capacity of soil for uranium. Moreover, the presence of carbonate decreased the sorption of U(VI onto soil because of the role of the strong complexation of carbonate with U(VI in the groundwater. Overall, this study assessed the behavior of U(VI sorption onto natural soil, which would be an important factor in the geological barrier of the repository, has contribution on mastering the characteristic of the adsorption of uranium in the particular soil media for the process of very low level radioactive waste disposal.

Construction of Basic Evaluation Criteria for Candidate HLW Repository Sites (1)

International Nuclear Information System (INIS)

Koh, Yong Kwon; Bae, Dae Seok; Kim, Kyung Su; Kim, Geon Young; Park, Kyung Woo; Ji, Sung Hoon; Ryu, Ji Hun

2009-08-01

We constructed the preliminary site assessment system for selection of proper site as high level radioactive disposal repository with consideration of Korean geological characteristics and underground environments. And, site assessment factor and standard as a point of geologic aspect were suggested for decision of candidate radioactive disposal site in Korea. The results can be used to develop the geological information system for assessment of candidate disposal site

Execution techniques and approach for high level radioactive waste disposal in Japan: Demonstration of geological disposal techniques and implementation approach of HLW project

International Nuclear Information System (INIS)

Kawanishi, M.; Komada, H.; Kitayama, K.; Akasaka, H.; Tsuchi, H.

2001-01-01

In Japan, the high-level radioactive waste (HLW) disposal project is expected to start fully after establishment of the implementing organization, which is planned around the year 2000 and to dispose the wastes in the 2030s to at latest in the middle of 2040s. Considering each step in the implementation of the HLW disposal project in Japan, this paper discusses the execution procedure for HLW disposal project, such as the selection of candidate/planned disposal sites, the construction and operation of the disposal facility, the closure and decommissioning of facilities, and the institutional control and monitoring after the closure of disposal facility, from a technical viewpoint for the rational execution of the project. Furthermore, we investigate and propose some ideas for the concept of the design of geological disposal facility, the validation and demonstration of the reliability on the disposal techniques and performance assessment methods at a candidate/planned site. Based on these investigation results, we made clear a milestone for the execution of the HLW disposal project in Japan. (author)

The disposal of Canada's nuclear fuel waste: site screening and site evaluation technology

International Nuclear Information System (INIS)

Davison, C.C.; Brown, A.; Everitt, R.A.; Gascoyne, M.; Kozak, E.T.; Lodha, G.S.; Martin, C.D.; Soonawala, N.M.; Stevenson, D.R.; Thorne, G.A.; Whitaker, S.H.

1994-06-01

The concept for the disposal of Canada's nuclear fuel waste is to dispose of the waste in an underground vault, nominally at 500 m to 1000 m depth, at a suitable site in plutonic rock of the Canadian Shield. The feasibility of this concept and assessments of its impact on the environment and human health, will be documented by AECL in an Environmental Impact Statement (EIS). This report is one of nine primary references for the EIS. It describes the approach and methods that would be used during the siting stage of the disposal project to identify a preferred candidate disposal site and to confirm its suitability for constructing a disposal facility. The siting stage is divided into two distinct but closely related substages, site screening and site evaluation. Site screening would mainly involve reconnaissance investigations of siting regions of the Shield to identify potential candidate areas where suitable vault locations are likely to exist. Site screening would identify a small number of candidate areas where further detailed investigations were warranted. Site evaluation would involve progressively more detailed surface and subsurface investigations of the candidate areas to first identify potentially suitable vault locations within the candidate areas, and then characterize these potential disposal sites to identify the preferred candidate location for constructing the disposal vault. Site evaluation would conclude with the construction of exploratory shafts and tunnels at the preferred vault location, and underground characterization would be done to confirm the suitability of the preferred candidate site. An integrated program of geological, geophysical, hydrogeological, geochemical and geomechanical investigations would be implemented to obtain the geoscience information needed to assess the suitability of the candidate siting areas and candidate sites for locating a disposal vault. The candidate siting areas and candidate disposal vault sites would be

Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong

Energy Technology Data Exchange (ETDEWEB)

Setiawan, Budi, E-mail: bravo@batan.go.id [Radwaste Technology Center-National Nuclear Energy Agency, PUSPIPTEK, Serpong-Tangerang 15310 (Indonesia); Mila, Oktri; Safni [Dept. of Chemistry, Fac. of Math. and Nat. Sci., Andalas University, Kampus Limau Manis, Padang-West Sumatra 25163 (Indonesia)

2014-03-24

Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr{sup +} ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10{sup −2} g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

Waste disposal of HYLIFE II structure: Issues and assessment

International Nuclear Information System (INIS)

Lee, J.D.

1992-01-01

Initial analysis has shown that by using 304 stainless steel (SS) a significant fraction (92 wt%) of the structural mass in the initial HYLIFE-II design could be disposed of by shallow burial. And if all the structural components are mixed together and treated as one entity, all of it could be disposed of by shallow burial. Two other types of SSs assessed, Mn-modified 316 and Prime Candidate Alloy (PCA), were found to require disposal by deep geologic burial of most of the structural mass. The presents of Nb and Mo in Mn-modified 316 and Prime Candidate Alloy (PCA), were found to dominate the generation of long term wastes produced and their presence should be avoided

Quantitative mineralogy and preliminary pore-water chemistry of candidate buffer and backfill materials for a nuclear fuel waste disposal vault

International Nuclear Information System (INIS)

Quigley, R.M.

1984-07-01

The quantitative mineralogy of seven candidate buffer and backfill materials for a nuclear fuel waste disposal vault is presented. Two of the materials were coarse grained: one a blended very pure silica sand, and the other a crushed plagioclase-rich granite or granodiorite. Five materials were fine-grained soils containing abundant clay minerals. Of these, three were fairly pure, Cretaceous, ash-derived bentonites that contained up to 3 percent of soluble sulphates; one was a freshwater glacial clay containing 59 percent interlayered smectite-illite; and one was a crushed Paleozoic shale containing abundant illite and chlorite. The adsorbed cation regimes and the pore-water chemistry of the clays are discussed

Waste disposal

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects

Waste disposal options report. Volume 2

International Nuclear Information System (INIS)

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k eff for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes

Waste disposal options report. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k{sub eff} for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes.

High-level waste processing and disposal

International Nuclear Information System (INIS)

Crandall, J.L.; Krause, H.; Sombret, C.; Uematsu, K.

1984-01-01

The national high-level waste disposal plans for France, the Federal Republic of Germany, Japan, and the United States are covered. Three conclusions are reached. The first conclusion is that an excellent technology already exists for high-level waste disposal. With appropriate packaging, spent fuel seems to be an acceptable waste form. Borosilicate glass reprocessing waste forms are well understood, in production in France, and scheduled for production in the next few years in a number of other countries. For final disposal, a number of candidate geological repository sites have been identified and several demonstration sites opened. The second conclusion is that adequate financing and a legal basis for waste disposal are in place in most countries. Costs of high-level waste disposal will probably add about 5 to 10% to the costs of nuclear electric power. The third conclusion is less optimistic. Political problems remain formidable in highly conservative regulations, in qualifying a final disposal site, and in securing acceptable transport routes

Low-level waste disposal site selection demonstration

International Nuclear Information System (INIS)

Rogers, V.C.

1984-01-01

This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

Development of very low-level radioactive waste sequestration process criteria

Energy Technology Data Exchange (ETDEWEB)

Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2015-12-15

Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

Updated candidate list for engineered barrier materials

International Nuclear Information System (INIS)

McCright, R.D.

1995-10-01

This report describes candidate materials to be evaluated over the next several years during advanced design phases for the waste package to be used for the underground disposal of high-level radioactive wastes at the Yucca Mountain facility

Identification of sites for the low-level waste disposal development and demonstration program

International Nuclear Information System (INIS)

Ketelle, R.H.; Lee, D.W.

1988-04-01

This report presents the results of site selection studies for potential low-level radioactive waste disposal sites on the Oak Ridge Reservation (ORR). Summaries of the site selection procedures used and results of previous site selection studies on the ORR are included. This report includes recommendations of sites for demonstration of shallow land burial using engineered trench designs and demonstration of above-grade disposal using design concepts similar to those used in tumulus disposal. The site selection study, like its predecessor (ORNL/TM-9717, Use of DOE Site Selection Criteria for Screening Low-Level Waste Disposal Sites on the Oak Ridge Reservation), involved application of exclusionary site screening criteria to the region of interest to eliminate unacceptable areas from consideration. Also like the previous study, the region of interest for this study was limited to the Oak Ridge Department of Energy Reservation. Reconnaissance-level environmental data were used in the study, and field inspections of candidate sites were made to verify the available reconnaissance data. Five candidate sites, all underlain by Knox dolomite residuum and bedrock, were identified for possible development of shallow land burial facilities. Of the five candidate sites, the West Chestnut site was judged to be best suited for deployment of the shallow land burial technology. Three candidate sites, all underlain by the Conasauga Group in Bear Creek Valley, were identified for possible development of above-grade disposal technologies. Of the three sites identified, the Central Bear Creek Valley site lying between State Route 95 and Gum Hollow Road was ranked most favorable for deployment of the above-grade disposal technology

Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site

International Nuclear Information System (INIS)

Price, L.

1994-09-01

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE's Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS

An annotated history of container candidate material selection

International Nuclear Information System (INIS)

McCright, R.D.

1988-07-01

This paper documents events in the Nevada Nuclear Waste Storage Investigations (NNWSI) Project that have influenced the selection of metals and alloys proposed for fabrication of waste package containers for permanent disposal of high-level nuclear waste in a repository at Yucca Mountain, Nevada. The time period from 1981 to 1988 is covered in this annotated history. The history traces the candidate materials that have been considered at different stages of site characterization planning activities. At present, six candidate materials are considered and described in the 1988 Consultation Draft of the NNWSI Site Characterization Plan (SCP). The six materials are grouped into two alloy families, copper-base materials and iron to nickel-base materials with an austenitic structure. The three austenitic candidates resulted from a 1983 survey of a longer list of candidate materials; the other three candidates resulted from a special request from DOE in 1984 to evaluate copper and copper-base alloys. 24 refs., 2 tabs

Normal evolution of a spent fuel repository at the candidate sites in Finland

International Nuclear Information System (INIS)

Grawford, M.B.; Wilmot, R.D.

1998-12-01

The Finnish disposal concept for spent nuclear fuel envisages burial of the fuel in a repository excavated at a depth of around 500 m in crystalline bedrock. Since 1983, a programme has been underway in Finland to select a potential site for such a repository. The programme is now in the final stages of selecting one site for further detailed characterisation from a list of four candidate sites at Kivetty, Romuvaara, Olkiluoto, and Haestholmen. Each stage of the site selection process has been supported by a major performance assessment (PA) exercise. The aim of this report is to describe the normal evolution of a repository system at the four candidate Finnish sites as input to development of the next PA, known as TILA-99. The report summarises the disposal concept and the present-day characteristics of each candidate site, and considers the most likely future changes in both the natural environment and the engineered components of the disposal system. The description concentrates on the key features, events and processes (FEPs) controlling behaviour and evolution of the disposal system. It is assumed that all the canisters are intact following emplacement and repository closure. FEPs that occur but which do not significantly affect system behaviour and evolution are only briefly described. FEPs with a low probability of occurrence are mentioned as appropriate. The report provides a map to the key Finnish reports and other work that underlies and supports the description of normal evolution. Differences between the four candidate sites in terms of their expected normal evolution are summarised. None of the differences are sufficient to prevent each site from behaving as a 'normal' site, the evolution of which is summarised over time in the final section of the report. (author)

Normal evolution of a spent fuel repository at the candidate sites in Finland

Energy Technology Data Exchange (ETDEWEB)

Grawford, M.B.; Wilmot, R.D. [Galson Sciences Limited, Rutland (United Kingdom)

1998-12-01

The Finnish disposal concept for spent nuclear fuel envisages burial of the fuel in a repository excavated at a depth of around 500 m in crystalline bedrock. Since 1983, a programme has been underway in Finland to select a potential site for such a repository. The programme is now in the final stages of selecting one site for further detailed characterisation from a list of four candidate sites at Kivetty, Romuvaara, Olkiluoto, and Haestholmen. Each stage of the site selection process has been supported by a major performance assessment (PA) exercise. The aim of this report is to describe the normal evolution of a repository system at the four candidate Finnish sites as input to development of the next PA, known as TILA-99. The report summarises the disposal concept and the present-day characteristics of each candidate site, and considers the most likely future changes in both the natural environment and the engineered components of the disposal system. The description concentrates on the key features, events and processes (FEPs) controlling behaviour and evolution of the disposal system. It is assumed that all the canisters are intact following emplacement and repository closure. FEPs that occur but which do not significantly affect system behaviour and evolution are only briefly described. FEPs with a low probability of occurrence are mentioned as appropriate. The report provides a map to the key Finnish reports and other work that underlies and supports the description of normal evolution. Differences between the four candidate sites in terms of their expected normal evolution are summarised. None of the differences are sufficient to prevent each site from behaving as a `normal` site, the evolution of which is summarised over time in the final section of the report. (author) 155 refs.

Ocean disposal of heat generating radioactive waste backfilling requirements

International Nuclear Information System (INIS)

1986-07-01

This report describes the backfilling requirements arising from the disposal of HGW in deep ocean sediments. The two disposal options considered are the drilled emplacement method and the free fall penetrator method. The materials best suited for filling the voids in the two options are reviewed. Candidate materials are selected following a study of the property requirements of each backfill. Placement methods for the candidate materials, as well as the means available for verifying the quality of the filling, are presented. Finally, an assessment of the overall feasibility of each placement method is given. The main conclusion is that, although the proposed methods are feasible, further work is necessary to test in inactive trials each of the proposed filling methods. Moreover, it is difficult to envisage how two of the backfilling operations in drilled emplacement option can be verified by non destructive methods. (author)

Preparation of Potentially Site Candidate of Radioactive Waste Disposal in Java Island and Its Surrounding Areas

International Nuclear Information System (INIS)

Budi Setiawan

2008-01-01

Introduction plan of NPP in Indonesia raised public attentions specially for its radwaste management and its disposal activity. In the next 5 year (2007-2011) will be provided some sites for radwaste disposal, both for near surface disposal and geological disposal systems with suitable and safely based on the IAEA standard. To find out a save and suitable location, field investigation programme is needed. Prior entering into investigation programme, preliminary activities are necessary to be arranged such as secondary data collecting: identification of host rock, interest areas, objectives and investigation programmes. Through desktop study with limited references hopefully information of some areas in Java Island with widely enough, thick and exposed into surface of clay deposit indication could be obtained. Objective of the activity is to prepare important supporting data before actualize as a field survey programme. Results showed that secondary data such as rock identification, interest areas, objectives and investigation programmes are found out. (author)

Disposal of spent fuel

International Nuclear Information System (INIS)

Blomeke, J.O.; Ferguson, D.E.; Croff, A.G.

1978-01-01

Based on preliminary analyses, spent fuel assemblies are an acceptable form for waste disposal. The following studies appear necessary to bring our knowledge of spent fuel as a final disposal form to a level comparable with that of the solidified wastes from reprocessing: 1. A complete systems analysis is needed of spent fuel disposition from reactor discharge to final isolation in a repository. 2. Since it appears desirable to encase the spent fuel assembly in a metal canister, candidate materials for this container need to be studied. 3. It is highly likely that some ''filler'' material will be needed between the fuel elements and the can. 4. Leachability, stability, and waste-rock interaction studies should be carried out on the fuels. The major disadvantages of spent fuel as a disposal form are the lower maximum heat loading, 60 kW/acre versus 150 kW/acre for high-level waste from a reprocessing plant; the greater long-term potential hazard due to the larger quantities of plutonium and uranium introduced into a repository; and the possibility of criticality in case the repository is breached. The major advantages are the lower cost and increased near-term safety resulting from eliminating reprocessing and the treatment and handling of the wastes therefrom

Earth reencounter probabilities for aborted space disposal of hazardous nuclear waste

Science.gov (United States)

Friedlander, A. L.; Feingold, H.

1977-01-01

A quantitative assessment is made of the long-term risk of earth reencounter and reentry associated with aborted disposal of hazardous material in the space environment. Numerical results are presented for 10 candidate disposal options covering a broad spectrum of disposal destinations and deployment propulsion systems. Based on representative models of system failure, the probability that a single payload will return and collide with earth within a period of 250,000 years is found to lie in the range .0002-.006. Proportionately smaller risk attaches to shorter time intervals. Risk-critical factors related to trajectory geometry and system reliability are identified as possible mechanisms of hazard reduction.

Review on waste inventory, waste characteristics and candidate site for LLW disposal in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sriyotha, P.; Punnachaiya, M.; Danladkaew, K.

1997-01-01

It is a worldwide practice that radioactive waste has to be kept under control to be ensured of low potential impact on man and his environment. In Thailand, the OAEP is responsible for all radioactive waste management activities, both operation and the competent authority. The radioactive waste in Thailand consists of low level wastes from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. A plan for central disposal site has been set up. The near surface disposal method is chosen for this aspect because of its simple, inexpensive and adequate safe and very well know process. 8 refs., 6 tabs

Status of the high-level nuclear waste disposal program in Japan

International Nuclear Information System (INIS)

Uematsu, K.

1985-01-01

The Japan Atomic Energy Commission (JAEC) initiated a high-level radioactive waste disposal program in 1976. Since then, the Advisory Committee on Radioactive Waste Management of JAEC has revised the program twice. The latest revision was issued in 1984. The committee recommended a four-phase program and the last phase calls for the beginning of emplacement of the high-level nuclear waste into a selected repository in the Year 2000. The first phase is already completed, and the second phase of this decade calls for the selection of a candidate disposal site and the conducting of the RandD of waste disposal in an underground research laboratory and in a hot test facility. This paper covers the current status of the high-level nuclear waste disposal program in Japan

Choice of french clays as engineered barrier components for waste disposal

International Nuclear Information System (INIS)

Coulon, H.; Lajudie, A.; Debrabant, P.; Atabek, R.; Jorda, M.; Andre-Jehan, R.

1987-01-01

Results are presented of physical measurements on candidate buffer materials for use in nuclear fuel waste disposal. The materials being considered as constituent elements of engineered barriers are essentially calcium smectite clays, in other terms swelling clays, coming from fourteen french deposits. The criteria for good candidates are mainly: smectite content in the clay materials, carbonate and organic material content and bulk density of the material, compacted under a pressure of 100 MPa. 14 references, 4 figures, 6 tables

Necessary contents of public outreach for high level radioactive waste disposal

International Nuclear Information System (INIS)

Kanzaki, Noriko; Okamoto, Koji

2011-01-01

Nuclear power generation is one of the solutions for global warming. However, the nuclear power generation technology can not be completed unless the disposal method of the radioactive waste is decided. Various actions are performed about the High Level Radioactive Waste (HLW) disposal in particular in each country. However, planning of HLW disposal site was not successful, except Finland and Sweden. In Japan, geological disposal of HLW was selected. The operating body and the capital management body are also decided. Up to the present, no municipality apply the disposal site candidate. An important social element for HLW disposal is careful explanation and communication for municipality. For this purpose, a symposium to explain necessity of HLW is held in each district in Japan. The symposium is not successful, because of lack of carefulness to local situation considered. In this study, we evaluates the questionnaire by the symposium attendee to extract the idea and requests by the local people. With these questionnaire, the responsibility of the government should be more enhanced. Also, the detail answer to the people's questions are needed. Using these knowledge, the HLW disposal social acceptance has been discussed. (author)

Selection of low-level radioactive waste disposal sites using screening models versus more complex methodologies

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.

1993-01-01

The task of choosing a waste-disposal site from a set of candidate sites requires an approach capable of objectively handling many environmental variables for each site. Several computer methodologies have been developed to assist in the process of choosing a site for the disposal of low-level radioactive waste; however, most of these models are costly to apply, in terms of computer resources and the time and effort required by professional modelers, geologists, and waste-disposal experts. The authors describe how the relatively simple DRASTIC methodology (a standardized system for evaluating groundwater pollution potential using hydrogeologic settings) may be used for open-quotes pre-screeningclose quotes of sites to determine which subset of candidate sites is worthy of more detailed screening. Results of site comparisons made with DRASTIC are compared with results obtained using PRESTO-II methodology, which is representative of the more complex release-transport-human exposure methodologies. 6 refs., 1 fig., 1 tab

Determining the suitability of materials for disposal at sea under the London Convention 1972: A radiological assessment procedure

International Nuclear Information System (INIS)

2003-10-01

The Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (London Convention 1972) prohibits the disposal at sea of radioactive wastes and other radioactive matter. However natural radionuclides are present in all materials, including natural and inert materials, which can also contain artificial radionuclides from anthropogenic sources such as fallout due to past atmospheric nuclear testing. Therefore, the Contracting Parties to the London Convention 1972 recognized the need to develop definitions and guidelines so that candidate materials (those wastes or other matter not otherwise prohibited from disposal at sea in accordance with Annex I to the Convention) containing less than de minimis levels of specific activity, can be regarded as 'non-radioactive' and may be disposed of at sea subject to the other provisions of the Convention. At the Nineteenth Consultative Meeting in 1997, Contracting Parties to the London Convention 1972 agreed to request the IAEA to develop further the concept of de minimis levels and, in particular, to 'provide guidance for making judgements on whether materials planned to be dumped could be exempted from radiological control or whether a specific assessment was needed' (LC 19/10, paragraph 6.31). This paragraph continues: 'The IAEA would then further be requested to provide guidance to national authorities responsible for conducting specific assessments.' The IAEA presented its advice on de minimis in IAEA-TECDOC-1068, entitled Application of Radiological Exclusion and Exemption Principles to Sea Disposal, to the Twenty-first Consultative Meeting of Contracting Parties to the London Convention 1972 in October 1999. The Contracting Parties accepted these principles and criteria and interpreted them further in the Guidelines for the Application of the De Minimis Concept Under the London Convention 1972 (the Guidelines). At that time, the Contracting Parties asked the IAEA to prepare additional guidance

Siting Study for the Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Progress in welding studies for Canadian nuclear fuel waste disposal containers

International Nuclear Information System (INIS)

Maak, P.Y.Y.

1985-11-01

This report describes the progress in the development of closure-welding technology for Canadian nuclear fuel waste disposal containers. Titanium, copper and Inconel 625 are being investigated as candidate materials for fabrication of these containers. Gas-tungsten-arc welding, gas metal-arc-welding, resistance-heated diffusion bonding and electron beam welding have been evaluated as candidate closure welding processes. Characteristic weldment properties, relative merits of welding techniques, suitable weld joint configurations and fit-up tolerances, and welding parameter control ranges have been identified for various container designs. Furthermore, the automation requirements for candidate welding processes have been assessed. Progress in the development of a computer-controlled remote gas-shielded arc welding system is described

INPP Landfill

International Nuclear Information System (INIS)

Dahlberg, Jan; Bergstroem, Ulla

2004-06-01

The objective of this report is to propose the basic design for final disposal of Very Low Level Radioactive Waste (VLLW) produced at the Ignalina Nuclear Power Plant and at other small waste producers in Lithuania. Considering the safety for the environment, as well as the construction costs, it has been decided that the repository will be of a landfill type based on the same design principles as similar authorised facilities in other countries. It has also been decided that the location of the landfill shall be in the vicinity of the Ignalina Nuclear Power Plant (INPP)

Geological factors of disposal site selection for low-and intermediate-level solid radwastes in China

International Nuclear Information System (INIS)

Chen Zhangru

1993-01-01

For disposal of low- and intermediate-level solid radioactive wastes, shallow-ground disposal can provide adequate isolation of waste from human for a fairly long period of time. The objective of disposal site selection is to ensure that the natural properties of the site together with the engineered barrier site shall provide adequate isolation of radionuclides from the human beings and environment, so the whole disposal system can keep the radiological impact within an acceptable level. Since the early 1980's, complying with the national standards and the expert's conception as well as the related IAEA Criteria, geological selection of disposal sites for low-and intermediate-level solid radwastes has been carried out in East China, South China, Northwest China and Southwest China separately. Finally, 5 candidate sites were recommended to the CNNC

MODIFIED APPROACH FOR SITE SELECTION OF UNWANTED RADIOACTIVE SEALED SOURCES DISPOSAL IN ARID COUNTRIES (CASE STUDY - EGYPT)

International Nuclear Information System (INIS)

ABDEL AZIZ, M.A.H.; COCHRAN, J.R.

2008-01-01

The aim of this study is to present a systematic methodology for siting of radioactive sealed sources disposal in arid countries and demonstrate the use of this methodology in Egypt. Availing from the experience gained from the greater confinement disposal (GCD) boreholes in Nevada, USA, the IAEA's approach for siting of near disposal was modified to fit the siting of the borehole disposal which suits the unwanted radioactive sealed sources. The modifications are represented by dividing the surveyed area into three phases; the exclusion phase in which the areas that meet exclusion criteria should be excluded, the site selection phase in which some potential sites that meet the primary criteria should be candidate and the preference stage in which the preference between the potential candidate sites should be carried out based on secondary criteria to select one or two sites at most. In Egypt, a considerable amount of unwanted radioactive sealed sources wastes have accumulated due to the peaceful uses of radio-isotopes.Taking into account the regional aspects and combining of the proposed developed methodology with geographic information system (GIS), the Nile Delta and its valley, the Sinai Peninsula and areas of historical heritage value are excluded from our concern as potential areas for radioactive waste disposal. Using the primary search criteria, some potential sites south Kharga, the Great Sand Sea, Gilf El-Kebear and the central part of the eastern desert have been identified as candidate areas meeting the primary criteria of site selection. More detailed studies should be conducted taking into account the secondary criteria to prefer among the above sites and select one or two sites at most

Waste management from reprocessing: a stringent regulatory requirements for high quality conditioned residues

International Nuclear Information System (INIS)

Bordier, J. C.; Greneche, D.; Devezeaux, J. G.; Dalcorso, J.

2000-01-01

Nuclear waste production and management in France is governed by safety requirements imposed to all operators. French nuclear safety relies on two basic principles: · Responsibility of the nuclear operator, which expands to waste generated, · Safety basic objectives issued by national Safety Authority. For a long time the regulatory framework for waste production and management has been satisfactorily applied and has benefited to each actor of the process. LLW/MLW and HLW nuclear waste are currently conditioned in safe matrices or packages either likely to be disposed in surface repositories or designed with the intention to be disposed underground according to their radioactive content. France is looking into the case of VLLW and has already carried out a design for future disposal, the design being in the pipe. Other types of waste (i. e. radium bearing waste, graphite, and tritium content waste) are also considered in the whole framework of French waste management. (author)

How a developing country is facing LLW disposal problem

International Nuclear Information System (INIS)

Huang, C.C.; Shao, Y.T.; Tsai, C.M.

1993-01-01

Taiwan is a small island which measures about 36,000 square kilometers with over 70% mountainous area. Today over 90% of low-level radioactive waste (LLW) is produced from six nuclear power units operated by the Taiwan Power Company (Taipower or TPC). The rest of the country's LLW is produced from medical, agricultural, industrial, educational and research programs. Due to the fact that over 90% of Taiwan's LLW is produced by Taipower, Taipower was designated by the Government to dispose of LLW for entire country. This paper will focus on the planning and implementation of the first phase. Through area screening and potential site evaluation, candidate sites will be selected based on currently available information and sites investigation. At the same time, the disposal methods will be evaluated in terms of safety, cost, and Taiwan's generic conditions of climate, geology, and topography. The conceptual design of the disposal method(s) will then be developed. Also, during site investigation, preliminary designs will be made

Sampling plan design and analysis for a low level radioactive waste disposal program

International Nuclear Information System (INIS)

Hassig, N.L.; Wanless, J.W.

1989-01-01

Low-level wastes that are candidates for BRC (below regulatory concern) disposal must be subjected to an extensive monitoring program to insure the wastes meet (potential) bulk property and contamination concentration BRC criteria for disposal. This paper addresses the statistical implications of using various methods to verify BRC criteria. While surface and volumetric monitoring each have their advantages and disadvantages, a dual, sequential monitoring process is the preferred choice from a statistical reliability perspective. With dual monitoring, measurements on the contamination are verifiable, and sufficient to allow for a complete characterization of the wastes. As these characterizations become more reliable and stable, something less than 100% sampling may be possible for release of wastes for BRC disposal. This paper provides a survey of the issues involved in the selection of a monitoring and sampling program for the disposal of BRC wastes

Geological disposal of heat generating radioactive waste

International Nuclear Information System (INIS)

1985-02-01

A study has been made of the requirements and design features for containers to isolate vitrified heat generating radioactive waste from the environment for a period of 500 to 1000 years. The requirements for handling, storing and transporting containers have been identified following a study of disposal operations, and the pressures and temperatures which may possibly be experienced in clay, granite and salt formations have been estimated. A range of possible container designs have been proposed to satisfy the requirements of each of the disposal environments. Alternative design concepts in corrosion resistant or corrosion allowance material have been suggested. Potentially suitable container shell materials have been selected following a review of corrosion studies and although metals have not been specified in detail, titanium alloys and low carbon steels are thought to be appropriate for corrosion resistant and corrosion allowance designs respectively. Performance requirements for container filler materials have been identified and candidate materials assessed. A preliminary container stress analysis has shown the importance of thermal modelling and that if lead is used as a filler it dominates the stress response of the container. Possible methods of manufacturing disposal containers have been assessed and found to be generally feasible. (author)

Evaluation and selection of candidate high-level waste forms

International Nuclear Information System (INIS)

1982-03-01

Seven candidate waste forms being developed under the direction of the Department of Energy's National High-Level Waste (HLW) Technology Program, were evaluated as potential media for the immobilization and geologic disposal of high-level nuclear wastes. The evaluation combined preliminary waste form evaluations conducted at DOE defense waste-sites and independent laboratories, peer review assessments, a product performance evaluation, and a processability analysis. Based on the combined results of these four inputs, two of the seven forms, borosilicate glass and a titanate based ceramic, SYNROC, were selected as the reference and alternative forms for continued development and evaluation in the National HLW Program. Both the glass and ceramic forms are viable candidates for use at each of the DOE defense waste-sites; they are also potential candidates for immobilization of commercial reprocessing wastes. This report describes the waste form screening process, and discusses each of the four major inputs considered in the selection of the two forms

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Energy Technology Data Exchange (ETDEWEB)

Farmer, J.C.; Van Konynenburg, R.A.; McCright, R.D. (Lawrence Livermore National Lab., CA (USA)); Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-04-01

Three iron- to nickel-based austenitic alloys (Types 304L and 316L stainless steels and Alloy 825) are being considered as candidate materials for the fabrication of high-level radioactive-waste containers. Waste will include fuel assemblies from reactors as well as high-level waste in borosilicate glass forms, and will be sent to the prospective repository at Yucca Mountain, Nevada. The decay of radionuclides in the repository will result in the generation of substantial heat and in fluences of gamma radiation. Container materials may undergo any of several modes of degradation in this environment, including atmospheric oxidation; uniform aqueous phase corrosion; pitting; crevice corrosion; sensitization and intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This report is an analysis of data relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of the three austenitic candidate alloys. The candidates are compared in terms of their susceptibilities to these forms of corrosion. Although all three candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these types of localized corrosion (LC); such resistance is important because pits can penetrate the metal and serve as crack initiation sites. Both Types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented in Alloy 825 under comparable conditions. Gamma radiation has been found to enhance SCC in Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while the effects of microbiologically induced corrosion have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. 211 refs., 49 figs., 10 tabs.

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Farmer, J.C.; Van Konynenburg, R.A.; McCright, R.D.; Bullen, D.B.

1988-04-01

Three iron- to nickel-based austenitic alloys (Types 304L and 316L stainless steels and Alloy 825) are being considered as candidate materials for the fabrication of high-level radioactive-waste containers. Waste will include fuel assemblies from reactors as well as high-level waste in borosilicate glass forms, and will be sent to the prospective repository at Yucca Mountain, Nevada. The decay of radionuclides in the repository will result in the generation of substantial heat and in fluences of gamma radiation. Container materials may undergo any of several modes of degradation in this environment, including atmospheric oxidation; uniform aqueous phase corrosion; pitting; crevice corrosion; sensitization and intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This report is an analysis of data relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of the three austenitic candidate alloys. The candidates are compared in terms of their susceptibilities to these forms of corrosion. Although all three candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these types of localized corrosion (LC); such resistance is important because pits can penetrate the metal and serve as crack initiation sites. Both Types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented in Alloy 825 under comparable conditions. Gamma radiation has been found to enhance SCC in Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while the effects of microbiologically induced corrosion have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. 211 refs., 49 figs., 10 tabs

Environmental impacts of ocean disposal of CO2

International Nuclear Information System (INIS)

Adams, E.; Herzog, H.; Auerbach, D.

1995-01-01

One option to reduce atmospheric CO 2 levels is to capture and sequester power plant CO 2 Commercial CO 2 capture technology, though expensive, exists today. However, the ability to dispose of large quantities of CO 2 is highly uncertain. The deep ocean is one of only a few possible CO 2 disposal options (others are depleted oil and gas wells or deep, confined aquifers) and is a prime candidate because the deep ocean is vast and highly unsaturated in CO 2 . The term disposal is really a misnomer because the atmosphere and ocean eventually equilibrate on a timescale of 1000 years regardless of where the CO 2 is originally discharged. However, peak atmospheric CO 2 concentrations expected to occur in the next few centuries could be significantly reduced by ocean disposal. The magnitude of this reduction will depend upon the quantity of CO 2 injected in the ocean, as well as the depth and location of injection. Ocean disposal of CO 2 will only make sense if the environmental impacts to the ocean are significantly less than the avoided impacts of atmospheric release. Our project has been examining these ocean impacts through a multi-disciplinary effort designed to summarize the current state of knowledge. The end-product will be a report issued during the summer of 1996 consisting of two volumes an executive summary (Vol I) and a series of six, individually authored topical reports (Vol II). A workshop with invited participants from the U.S. and abroad will review the draft findings in January, 1996

Thermal performance of a depleted uranium shielded storage, transportation, and disposal package

International Nuclear Information System (INIS)

Wix, S.D.; Yoshimura, H.R.

1994-01-01

The US Department of Energy (DOE) is responsible for management and disposal of large quantities of depleted uranium (DU) in the DOE complex. Viable economic options for the use and eventual disposal of the material are needed. One possible option is the use of DU as shielding material for vitrified Defense High-Level Waste (DHLW) storage, transportation, and disposal packages. Use of DU as a shielding material provides the potential benefit of disposing of significant quantities of DU during the DHLW storage and disposal process. Two DU package concepts have been developed by Sandia National Laboratories. The first concept is the Storage/Disposal plus Transportation (S/D+T) package. The S/D+T package consists of two major components: a storage/disposal (S/D) container and a transportation overpack. The second concept is the S/D/T package which is an integral storage, transportation, and disposal package. The package concept considered in this analysis is the S/D+T package with seven DHLW waste canisters. The S/D+T package provides shielding and containment for the DHLW waste canisters. The S/D container is intended to be used as an on-site storage and repository disposal container. In this analysis, the S/D container is constructed from a combination of stainless steel and DU. Other material combinations, such as mild steel and DU, are potential candidates. The transportation overpack is used to transport the S/D containers to a final geological repository and is not included in this analysis

Developing a LLW disposal facility in California

International Nuclear Information System (INIS)

Romano, S.A.; Gaynor, R.K.; Hanrahan, T.P.

1988-01-01

US Ecology has been designated by the State of California to site and operate a low-level radioactive waste disposal facility. The firm identified three sites for detailed characterization work in February, 1987. Ecological and archaeological studies and related environmental assessments were undertaken to obtain land use permits from the Bureau of Land Management, which holds title to the sites. Geophysics investigations, exploratory borings, well drilling and weather station installation followed. Local Committees were established for each site to assist US Ecology in evaluating socio-economic impacts, and Native Americans were consulted regarding cultural resources. The project's Citizens Advisory Committee assisted in evaluating the three candidate sites. US Ecology systematically integrated citizen involvement into the technical studies leading to selection of the two site finalists. This approach furthered two objectives. Community leaders and the public received accurate information on the nature of low-level radioactive waste and the environmental conditions appropriate for its disposal

Siting history and current construction status of disposal facility for low and intermediate level radioactive waste in Korea

International Nuclear Information System (INIS)

Sakai, Akihiro; Kikuchi, Saburo; Maruyama, Masakatsu

2008-01-01

Korean government decided disposal site for low and intermediate level radioactive waste (LILW), which is located at coastal area near the Wolsong nuclear power plants in Gyeong-Ju city in December. 2005, based on the result of votes of residents in four candidate sites. Since then, Korea Hydro and Nuclear Power Co., Ltd (KHNP), which is the management company of the LILW disposal facility, has carried out the preparation for construction of disposal facility and its licensing process. At the first phase, 100 thousand drums in 200 liter are planned to be disposed of in the rock cavern type disposal facility located at the depth from 80m to 130m below the sea level, and finally 800 thousand drums in 200 liter are planned to be disposed of in the site. This report shows the history of siting for the LILW disposal, the outline of design of disposal facility and current status of its construction, based on the information which was obtained mainly during our visit to the disposal site in Korea. (author)

Siting simulation for low-level waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Rope, R.C.

1985-01-01

The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

International Nuclear Information System (INIS)

THIELGES, J.R.; CHASTAIN, S.A.

2007-01-01

The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

Energy Technology Data Exchange (ETDEWEB)

THIELGES, J.R.; CHASTAIN, S.A.

2007-06-21

The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

Modeling of nuclear waste disposal by rock melting

International Nuclear Information System (INIS)

Heuze, F.E.

1982-04-01

Today, the favored option for disposal of high-level nuclear wastes is their burial in mined caverns. As an alternative, the concept of deep disposal by rock melting (DRM) also has received some attention. DRM entails the injection of waste, in a cavity or borehole, 2 to 3 kilometers down in the earth crust. Granitic rocks are the prime candidate medium. The high thermal loading initially will melt the rock surrounding the waste. Following resolidification, a rock/waste matrix is formed, which should provide isolation for many years. The complex thermal, mechanical, and hydraulic aspects of DRM can be studied best by means of numerical models. The models must accommodate the coupling of the physical processes involved, and the temperature dependency of the granite properties, some of which are subject to abrupt discontinuities, during α-β phase transition and melting. This paper outlines a strategy for such complex modeling

Waste and Disposal: Research and Development

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.

2002-01-01

This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to

Waste and Disposal: Research and Development

Energy Technology Data Exchange (ETDEWEB)

Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P

2002-04-01

This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to

Imaging the risks - risking the image: Social impact assessment of the final disposal facility

International Nuclear Information System (INIS)

Avolahti, J.; Vira, J.

1999-01-01

Preparations for the final disposal of spent nuclear fuel in Finland started about twenty years ago. At present the work is carried out by Posiva Oy, which in 1996 took over the programme managed earlier by Teollisuuden Voima Oy, one of the country's nuclear power companies. From 1996 on the preparations have been made for all the spent fuel from Finnish nuclear power stations. The site for the final disposal facility will be selected among four alternatives by the end of 2000 and - assuming that the technical approach proposed by Posiva is accepted by the Government and the Parliament - the construction of the repository will start in the 2010s. The disposal operations are planned to be started in 2020. The alternative four sites have gone through a systematic site selection process based on geologic siting criteria and on environmental and cultural considerations. One of the objectives of the process was to avoid inhabited areas, agricultural fields, valuable groundwater or preservation areas as well as areas which might draw interest as regards the potential for ore deposits. The idea was that the field investigations and later the possible disposal facility should not cause any harm to local people. Two of the candidate sites are at present nuclear power plant sites situated at the coast, the two other candidates are inland sites with no nuclear activities. The geologic siting investigations were started in 1987. Interim assessments of the results so far have been made in 1992 and 1996 and a final report of all the investigations will be published before the end of 2000. The present view is that all four candidates are geologically suitable for siting the repository. Posiva's EIA for the final disposal of spent fuel in Finland is nearing completion. A considerable effort was made to involve local groups and individuals in the assessment process. Yet the participation remained limited and consisted mainly of active opponents of the project and of those who were

Imaging the risks - risking the image: Social impact assessment of the final disposal facility

Energy Technology Data Exchange (ETDEWEB)

Avolahti, J.; Vira, J. [Posiva Oy, Helsinki (Finland)

1999-12-01

Preparations for the final disposal of spent nuclear fuel in Finland started about twenty years ago. At present the work is carried out by Posiva Oy, which in 1996 took over the programme managed earlier by Teollisuuden Voima Oy, one of the country's nuclear power companies. From 1996 on the preparations have been made for all the spent fuel from Finnish nuclear power stations. The site for the final disposal facility will be selected among four alternatives by the end of 2000 and - assuming that the technical approach proposed by Posiva is accepted by the Government and the Parliament - the construction of the repository will start in the 2010s. The disposal operations are planned to be started in 2020. The alternative four sites have gone through a systematic site selection process based on geologic siting criteria and on environmental and cultural considerations. One of the objectives of the process was to avoid inhabited areas, agricultural fields, valuable groundwater or preservation areas as well as areas which might draw interest as regards the potential for ore deposits. The idea was that the field investigations and later the possible disposal facility should not cause any harm to local people. Two of the candidate sites are at present nuclear power plant sites situated at the coast, the two other candidates are inland sites with no nuclear activities. The geologic siting investigations were started in 1987. Interim assessments of the results so far have been made in 1992 and 1996 and a final report of all the investigations will be published before the end of 2000. The present view is that all four candidates are geologically suitable for siting the repository. Posiva's EIA for the final disposal of spent fuel in Finland is nearing completion. A considerable effort was made to involve local groups and individuals in the assessment process. Yet the participation remained limited and consisted mainly of active opponents of the project and of those

Study on the background information for the geological disposal concept

International Nuclear Information System (INIS)

Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

2000-03-01

Japan Nuclear Cycle Development Institute (JNC) has published first R and D report in 1992, in which the fruits of the R and D work were compiled. Since then, JNC, has been promoting the second R and D progress report until before 2000, in which the background information on the geological disposal of high level radioactive waste (HLW) was to be presented as well as the technical basis. Recognizing the importance of the social consensus to the geological disposal, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. In this fiscal year, studies were divided into 2 phases, considering the time schedule of the second R and D progress report. 1. Phase 1: Analysis of the background information on the geological disposal concept. Based on the recent informations and the research works of last 2 years, final version of the study was made to contribute to the background informations for the second R and D progress report. (This was published in Nov. 1999 as the intermediate report: JNC TJ 1420 2000-006). 2. Phase 2: Following 2 specific items were selected for the candidate issues which need to be studied, considering the present circumstances around the R and D of geological disposal. (1) Educational materials and strategies related to nuclear energy and nuclear waste. Specific strategies and approaches in the area of nuclear energy and nuclear waste educational outreach and curriculum activities by the nuclear industry, government and other entities in 6 countries were surveyed and summarized. (2) Alternatives to geological disposal of HLW: Past national/international consideration and current status. The alternatives for the disposal of HLW have been discussed in the past and the major waste-producing countries have almost all chosen deep geological disposal as preferred method. Here past histories and recent discussions on the variations to geological disposal were studied. (author)

Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

International Nuclear Information System (INIS)

Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

1993-01-01

The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

Geological disposal of heat generating radioactive waste

International Nuclear Information System (INIS)

1986-03-01

A number of options for the disposal of vitrified heat-generating radioactive waste are being studied to ensure that safe methods are available when the time comes for disposal operations to commence. This study has considered the feasibility of three designs for containers which would isolate the waste from the environment for a minimum period of 500 to 1000 years. The study was sub-divided into the following major sections: manufacturing feasibility; stress analysis; integrity in accidents; cost benefit review. The candidate container designs were taken from the results of a previous study by Ove Arup and Partners (1985) and were developed as the study progressed. Their major features can be summarised as follows: (A) a thin-walled corrosion-resistant metal shell filled with lead or cement grout. (B) an unfilled thick-walled carbon steel shell. (C) an unfilled carbon steel shell planted externally with corrosion-resistant metal. Reference repository conditions in clay, granite and salt, reference disposal operations and metals corrosion data have been taken from various European Community radioactive waste management research and engineering projects. The study concludes that design Types A and B are feasible in manufacturing terms but design Type C is not. It is recommended that model containers should be produced to demonstrate the proposed methods of manufacture and that they should be tested to validate the analytical techniques used. (author)

Monitoring technologies for ocean disposal of radioactive waste

Science.gov (United States)

Triplett, M. B.; Solomon, K. A.; Bishop, C. B.; Tyce, R. C.

1982-01-01

The feasibility of using carefully selected subseabed locations to permanently isolate high level radioactive wastes at ocean depths greater than 4000 meters is discussed. Disposal at several candidate subseabed areas is being studied because of the long term geologic stability of the sediments, remoteness from human activity, and lack of useful natural resources. While the deep sea environment is remote, it also poses some significant challenges for the technology required to survey and monitor these sites, to identify and pinpoint container leakage should it occur, and to provide the environmental information and data base essential to determining the probable impacts of any such occurrence. Objectives and technical approaches to aid in the selective development of advanced technologies for the future monitoring of nuclear low level and high level waste disposal in the deep seabed are presented. Detailed recommendations for measurement and sampling technology development needed for deep seabed nuclear waste monitoring are also presented.

Reducing the tritium inventory in waste produced by fusion devices

Energy Technology Data Exchange (ETDEWEB)

Pamela, J., E-mail: jerome.pamela@cea.fr [CEA, Agence ITER-France, F-13108 Saint-Paul-lez-Durance (France); Decanis, C. [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Canas, D. [CEA, DEN/DADN, Centre de Saclay, F-91191 Gif-sur-Yvette cedex (France); Liger, K.; Gaune, F. [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France)

2015-04-15

Highlights: • Fusion devices including ITER will generate tritiated waste, some of which will need to be detritiated before disposal. • Interim storage is the reference solution offering an answer for all types of tritiated radwaste. • Incineration is very attractive for VLLW and possibly SL-LILW soft housekeeping waste, since it offers higher tritium and waste volume reduction than the alternative thermal treatment technique. • For metallic waste, further R&D efforts should be made to optimize tritium release management and minimize the need for interim storage. - Abstract: The specific issues raised by tritiated waste resulting from fusion machines are described. Of the several categories of tritium contaminated waste produced during the entire lifespan of a fusion facility, i.e. operating phase and dismantling phase, only two categories are considered here: metal components and solid combustible waste, especially soft housekeeping materials. Some of these are expected to contain a high level of tritium, and may therefore need to be processed using a detritiation technique before disposal or interim storage. The reference solution for tritiated waste management in France is a 50-year temporary storage for tritium decay, with options for reducing the tritium content as alternatives or complement. An overview of the strategic issues related to tritium reduction techniques is proposed for each radiological category of waste for both metallic and soft housekeeping waste. For this latter category, several options of detritiation techniques by thermal treatment like heating up or incineration are described. A comparison has been made between these various technical options based on several criteria: environment, safety, technical feasibility and costs. For soft housekeeping waste, incineration is very attractive for VLLW and possibly SL-LILW. For metallic waste, further R&D efforts should be conducted.

Technical framework to facilitate foreign spent fuel storage and geologic disposal in Russia

International Nuclear Information System (INIS)

Jardine, L.J.; Halsey, W.G.; Cmith, C.F.

2000-01-01

The option of storage and eventual geologic disposal in Russia of spent fuel of US origin used in Taiwan provides a unique opportunity that can benefit many parties. Taiwan has a near term need for a spent fuel storage and geologic disposal solution, available financial resources, but limited prospect for a timely domestic solution. Russia has significant spent fuel storage and transportation management experience, candidate storage and repository sites, but limited financial resources available for their development. The US has interest in Taiwan energy security, national security and nonproliferation interests in Russian spent fuel storage and disposal and interest in the US origin fuel. While it is understood that such a project includes complex policy and international political issues as well as technical issues, the goal of this paper is to begin the discussion by presenting a technical path forward to establish the feasibility of this concept for Russia

Corrosion of container materials for disposal of high-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Chun, K.S.; Park, H.S.; Yeon, J.W.; Ha, Y.K. [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-01-01

In the corrosion aspect of container for the deep geological disposal of high-level radioactive waste, disposal concepts and the related container materials, which have been developed by advanced countries, have been reviewed. The disposal circumstances could be divided into the saturated and the unsaturated zones. The candidate materials in the countries, which consider the disposal in the unsaturated zone, are the corrosion resistant materials such as supper alloys and stainless steels, but those in the saturated zone is cupper, one of the corrosion allowable materials. By the results of the pitting corrosion test of sensitized stainless steels (such as 304, 304L, 316 and 316L), pitting potential is decreased with the degree of sensitization and the pitting corrosion resistance of 316L is higher than others. And so, the long-term corrosion experiment with 316L stainless steel specimens, sebsitized and non-sensitized, under the compacted bentonite and synthetic granitic groundwater has been being carried out. The results from the experiment for 12 months indicate that no evidence of pitting corrosion of the specimens has been observed but the crevice corrosion has occurred on the sensitized specimens even for 3 months. (author). 33 refs., 19 figs., 10 tabs.

California LLW disposal site development update: Ahead of milestone schedule

International Nuclear Information System (INIS)

Romano, S.A.; Gaynor, R.K.

1987-01-01

US Ecology has been designated by the State of California to locate, develop and operate a low-level radioactive waste disposal facility. In early 1986, the firm identified eighteen desert basins in southeastern California for siting consideration. Three candidate sites were selected for detailed field characterization work in February, 1987. A preferred site for licensing purposes will be identified in early 1988. California is currently ahead of the siting milestone schedule mandated by the Low-Level Radioactive Waste Policy Amendments Act. It is likely that a license application will be filed before the 1990 milestone date. This paper describes the process undertaken by US Ecology to identify three candidates sites for characterization, and the public involvement program supporting this decision. Future activities leading to final site development are also described

Environmental impacts of ocean disposal of CO{sub 2}

Energy Technology Data Exchange (ETDEWEB)

Adams, E.; Herzog, H.; Auerbach, D. [and others

1995-11-01

One option to reduce atmospheric CO{sub 2} levels is to capture and sequester power plant CO{sub 2} Commercial CO{sub 2} capture technology, though expensive, exists today. However, the ability to dispose of large quantities of CO{sub 2} is highly uncertain. The deep ocean is one of only a few possible CO{sub 2} disposal options (others are depleted oil and gas wells or deep, confined aquifers) and is a prime candidate because the deep ocean is vast and highly unsaturated in CO{sub 2}. The term disposal is really a misnomer because the atmosphere and ocean eventually equilibrate on a timescale of 1000 years regardless of where the CO{sub 2} is originally discharged. However, peak atmospheric CO{sub 2} concentrations expected to occur in the next few centuries could be significantly reduced by ocean disposal. The magnitude of this reduction will depend upon the quantity of CO{sub 2} injected in the ocean, as well as the depth and location of injection. Ocean disposal of CO{sub 2} will only make sense if the environmental impacts to the ocean are significantly less than the avoided impacts of atmospheric release. Our project has been examining these ocean impacts through a multi-disciplinary effort designed to summarize the current state of knowledge. The end-product will be a report issued during the summer of 1996 consisting of two volumes an executive summary (Vol I) and a series of six, individually authored topical reports (Vol II). A workshop with invited participants from the U.S. and abroad will review the draft findings in January, 1996.

10 CFR 61.52 - Land disposal facility operation and disposal site closure.

Science.gov (United States)

2010-01-01

... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.52 Land disposal... wastes by placing in disposal units which are sufficiently separated from disposal units for the other... between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer zone...

Preliminary disposal limits, plume interaction factors, and final disposal limits

Energy Technology Data Exchange (ETDEWEB)

Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2018-01-11

In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

Final disposal of spent fuel in the Finnish bedrock

International Nuclear Information System (INIS)

1992-12-01

Teollisuuden Voima Oy (TVO) is preparing for the final disposal of spent nuclear fuel from the Olkiluoto nuclear power plant (TVO-I and TVO-II reactors). According to present estimates, a total of 1840 tU of spent fuel will be accumulated during the 40-year lifetime of the power plant. An interim storage facility for spent fuel (TVO-KPA Store) has operated at Olkiluoto since 1987. The spent fuel will be held in storage for several decades before it is shipped to the repository site. Both train and road transportation are possible. The spent fuel will be encapsulated in composite copper and steel canisters (ACP Canister) in a facility that will be build above the ground on the site where the repository is located. The repository will be constructed at the depth of several hundreds of meters in the bedrock. In 1987 five areas were selected for preliminary site investigations. The safety analysis (TVO-92) that was carried out shows that the proposed safety criteria would be met at each of the candidate sites. In future expected conditions there would never be significant releases of radioactive substances to the biosphere. The site investigations will be continued in the period 1993 to 2000. In parallel, a R and D programme will be devoted to the safety and technology of final disposal. The site for final disposal will be selected in the year 2000 with the aim of having the capability to start the disposal operations in 2020

Geosphere migration studies as support for the comparison of candidate sites for disposal of radioactive waste in rock-salt

International Nuclear Information System (INIS)

Glasbergen, P.; Hassanizadeh, S.M.; Noordijk, H.; Sauter, F.

1988-01-01

The Dutch research program on the geological disposal of radioactive waste was designed to supply a basis for the selection of combinations of three factors, i.e., type of rock-salt formation, site, and disposal technique, satisfying radiological standards and other criteria for final disposal. The potential sites have been grouped according to the type of rock-salt formation (e.g. bedded salt and salt domes) and two classes of depth below the surface of the ground. Values for geohydrological parameters were obtained by extrapolation of data from existing boreholes and analysis of the sedimentary environment. A three-dimensional model of groundwater flow and contaminant transport, called METROPOL, has been developed. To investigate the effect of high salinity on nuclide transport properly, a theoretical experimental study was carried out. Use of a thermodynamic approach showed that terms related to salt mass fraction have to be added to Darcy's and Fick's laws. An experimental study to investigate effects of these modifications is in progress. 8 refs.; 8 figs.; 1 table

Waste and Disposal: Research and Development

Energy Technology Data Exchange (ETDEWEB)

Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P

2001-04-01

This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2000 in three topical areas are reported on: performance assessments, waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. An impact assessment was completed for the radium storage facility at Olen (Belgium). Geological data, pumping rates and various hydraulic parameters were collected in support of the development of a new version of the regional hydrogeological model for the Mol site. Research and Development on waste forms and waste packages included both in situ and laboratory tests. Main emphasis in 2000 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to laboratory experiments, several large-scale migration experiments were performed in the HADES Underground Research Laboratory. In 2000, the TRANCOM Project to study the influence of dissolved organic matter on radionuclide migration as well as the RESEAL project to demonstrate shaft sealing were continued.

Waste and Disposal: Research and Development

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.

2001-01-01

This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2000 in three topical areas are reported on: performance assessments, waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. An impact assessment was completed for the radium storage facility at Olen (Belgium). Geological data, pumping rates and various hydraulic parameters were collected in support of the development of a new version of the regional hydrogeological model for the Mol site. Research and Development on waste forms and waste packages included both in situ and laboratory tests. Main emphasis in 2000 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to laboratory experiments, several large-scale migration experiments were performed in the HADES Underground Research Laboratory. In 2000, the TRANCOM Project to study the influence of dissolved organic matter on radionuclide migration as well as the RESEAL project to demonstrate shaft sealing were continued

Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

Energy Technology Data Exchange (ETDEWEB)

Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.

Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

International Nuclear Information System (INIS)

Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu

2016-01-01

In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea

Methodology for selecting low-level radioactive waste disposal sites with application to the Oak Ridge Reservation

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.

1984-01-01

A methodology was developed to select an environmentally acceptable site for low-level radioactive waste disposal for a predetermined region of interest using prescribed site suitability requirements. The methodology provides a defensible means for identifying candidate areas within the region, candidate sites within the areas, and an environmentally preferred site from the candidate sites. This is accomplished in site screening and site characterization stages. The site screening stage relies on reconnaissance data to identify a preferred site. The site characterization stage relies on a detailed site investigation to determine site acceptability. The methodology was applied to the US Department of Energy Oak Ridge Reservation through the site screening stage. 6 references, 3 figures, 7 tables

Real-time gamma imaging of technetium transport through natural and engineered porous materials for radioactive waste disposal.

Science.gov (United States)

Corkhill, Claire L; Bridge, Jonathan W; Chen, Xiaohui C; Hillel, Phil; Thornton, Steve F; Romero-Gonzalez, Maria E; Banwart, Steven A; Hyatt, Neil C

2013-12-03

We present a novel methodology for determining the transport of technetium-99m, a γ-emitting metastable isomer of (99)Tc, through quartz sand and porous media relevant to the disposal of nuclear waste in a geological disposal facility (GDF). Quartz sand is utilized as a model medium, and the applicability of the methodology to determine radionuclide transport in engineered backfill cement is explored using the UK GDF candidate backfill cement, Nirex Reference Vault Backfill (NRVB), in a model system. Two-dimensional distributions in (99m)Tc activity were collected at millimeter-resolution using decay-corrected gamma camera images. Pulse-inputs of ~20 MBq (99m)Tc were introduced into short (disposal of nuclear waste and potentially to a wide variety of other subsurface environments.

Execution techniques for high-level radioactive waste disposal. 2. Fundamental concept of geological disposal and implementing approach of disposal project

International Nuclear Information System (INIS)

Kawanishi, Motoi; Komada, Hiroya; Tsuchino, Susumu; Shiozaki, Isao; Kitayama, Kazumi; Akasaka, Hidenari; Inagaki, Yusuke; Kawamura, Hideki

1999-01-01

The making high activity of the high-level radioactive waste disposal business shall be fully started after establishing of the implementing organization which is planned around 2000. Considering each step of disposal business, in this study, the implementation procedure for a series of disposal business such as the selection of the disposal site, the construction and operation of the disposal facility, the closure and decommissioning of the disposal facility and the management after closure, which are carried forward by the implementation body is discussed in detail from the technical viewpoint and an example of the master schedule is proposed. Furthermore, we investigate and propose the concept of the geological disposal which becomes important in carrying forward to making of the business of the disposal, such as the present site selection smoothly, the fundamental idea of the safe securing for disposal, the basic idea to get trust to the disposal technique and the geological environmental condition which is the basic condition of this whole study for the disposal business making. (author)

Siting process for disposal site of low level radiactive waste in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sriyotha, P.; Thiengtrongjit, S.; Sriyotha, K.

1992-01-01

The radioactive waste in Thailand is composed of low level waste from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. In addition, the high activity of sealed radiation sources i.e. Cs-137 Co-60 and Ra-226 are also accumulated. Since the volume of treated waste has been gradually increased, the general needs for a repository become apparent. The near surface disposal method has been chosen for this aspect. The feasibility study on the underground disposal site has been done since 1982. The site selection criteria have been established, consisting of the rejection criteria, the technical performance criteria and the economic criteria. About 50 locations have been picked for consideration and 5 candidate sites have been selected and subsequent investigated. After thoroughly investigation, a definite location in Ratchburi Province, about 180 kilometers southwest of Bangkok, has been selected as the most suitable place for the near surface disposal of radioactive waste in Thailand

Underground disposal techniques of radioactive wastes and wind power generation in Europe

International Nuclear Information System (INIS)

Mori, Yoshiaki

2003-01-01

The 25th business report on foreign survey of electric power civil engineering technology. On the 25th foreign survey held by the Society of Electric Power Civil Engineering, Technology, disposal of high-level radioactive wastes (HLRWs) in Switzerland and Sweden, and wind power generation in Spain and Denmark were focused. As a result, it was found that opalinas clay and calcite under survey and investigation of host rock candidates for disposal of HLRWs are stable rock stratum with extremely low water permeability and without groundwater stream. At present, basic research and concrete disposing method are under advancement through actual scale tests. To obtain peoples' understanding on necessity, safety, cost-sharing, and so on of this business, it is essential to easily and precisely technical contents with high level generation specialty. And, on wind power generation, it is necessary to install wind wheels at a position enough to become maximum in wind energy usable from wind observation data and to maintain the wheel mechanically and electrically. Here were described outlines on the survey with its members and schedules. (G.K.)

Development and evaluation of candidate high-level waste forms

International Nuclear Information System (INIS)

Bernadzikowski, T.A.

1981-01-01

Some seventeen candidate waste forms have been investigated under US Department of Energy programs as potential media for the immobilization and geologic disposal of the high-level radioactive wastes (HLW) resulting from chemical processing of nuclear reactor fuels and targets. Two of these HLW forms were selected at the end of fiscal year (FY) 1981 for intensive development if FY 1982 to 1983. Borosilicate glass was continued as the reference form. A crystalline ceramic waste form, SYNROC, was selected for further product formulation and process development as the alternative to borosilicate glass. This paper describes the bases on which this decision was made

Geological aspects of a deep underground disposal facility in the Czech Republic

International Nuclear Information System (INIS)

Skopovy, J.; Woller, F.

1997-01-01

The basic requirements for the geological situation at a deep underground radioactive waste disposal site are highlighted, a survey of candidate host sites worldwide is presented, and the situation in the Czech Republic is analyzed. A 'General Project of Geological Activities Related to the Development of a Deep Underground Disposal Site for Radioactive Wastes and Spent Fuel in the Czech Republic' has been developed by the Nuclear Research Institute and approved and financed by the authorities. The Project encompasses the following stages: (i) preliminary study and research; (ii) examination of the seismicity, neotectonics, and geodynamics; (iii) search and critical assessment of archived geological information; (iv) non-destructive survey; and (v) destructive survey. The Project should take about 30 years and its scope will be updated from time to time. (P.A.)

Climate change research methods and its significance in the study of choosing candidate site in nuclear waste disposal sites

International Nuclear Information System (INIS)

Zhao Yong; Zhang Zhanshi

2008-01-01

A high-level nuclear waste is the inevitable product accompanies the development of the nuclear power station. How to dispose it properly has become focused by all over the world. Some of the important progresses have been achieved in the fields of site setting, performance assessment and underground laboratory recently. Palaeoclimate patter and the tendency of climate change are very important aspects for the site setting This paper discussed some of the important progresses on the disposal of unclear wastes, the influence of the climate change on the site setting and main methods such as lake sediments, marine sediment, loess, ancient soil and ice core deal with palaeoclimate and palaeo environment study. (authors)

Disposal safety

International Nuclear Information System (INIS)

Bartlett, J.W.

International consensus does not seem to be necessary or appropriate for many of the issues concerned with the safety of nuclear waste disposal. International interaction on the technical aspects of disposal has been extensive, and this interaction has contributed greatly to development of a consensus technical infrastructure for disposal. This infrastructure provides a common and firm base for regulatory, political, and social actions in each nation

French surface disposal experience. The disposal of large waste

International Nuclear Information System (INIS)

Dutzer, Michel; Lecoq, Pascal; Duret, Franck; Mandoki, Robert

2006-01-01

More than 90 percent of the volume of radioactive waste that are generated in France can be managed in surface disposal facilities. Two facilities are presently operated by ANDRA: the Centre de l'Aube disposal facility that is dedicated to low and intermediate short lived waste and the Morvilliers facility for very low level waste. The Centre de l'Aube facility was designed at the end of the years 1980 to replace the Centre de la Manche facility that ended operation in 1994. In order to achieve as low external exposure as possible for workers it was decided to use remote handling systems as much as possible. Therefore it was necessary to standardize the types of waste containers. But taking into account the fact that these waste were conditioned in existing facilities, it was not possible to change a major part of existing packages. As a consequence, 6 mobile roofs were constructed to handle 12 different types of waste packages in the disposal vaults. The scope of Centre de l'Aube was mainly to dispose operational waste. However some packages, as 5 or 10 m 3 metallic boxes, could be used for larger waste generated by decommissioning activities. The corresponding flow was supposed to be small. After the first years of operations, it appeared interesting to develop special procedures to dispose specific large waste in order to avoid external exposure costly cutting works in the generating facilities. A 40 m 3 box and a large remote handling device were disposed in vaults that were currently used for other types of packages. Such a technique could not be used for the disposal of vessel heads that were replaced in 55 pressurised water power reactors. The duration of disposal and conditioning operation was not compatible with the flow of standard packages that were delivered in the vaults. Therefore a specific type of vault was designed, including handling and conditioning equipment. The first pressure vessel head was delivered on the 29 of July 2004, 6 heads have been

The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

International Nuclear Information System (INIS)

Simmons, G.R.; Baumgartner, P.

1994-01-01

This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

Review of hydrodynamic and transport models and data collected near the mid-Atlantic low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Onishi, Y.; Hibler, L.F.; Sherwood, C.R.

1987-08-01

The objectives of this study were to (1) briefly review and evaluate available simulation models that may be used to predict the distribution of low-level radioactive waste (LLW) from the 2800-m and 3800-m Low Level Radioactive Disposal Sites in the Mid-Atlantic Continental Slope and Rise on a regional (a few hundred kilometers square) scale, (2) identify pertinent physical, biological, and geological oceanographic data in or near those LLW disposal sites, and (3) determine minimum data requirements for regional modeling. With suitable model modifications such as turbulence closure, enhanced sediment transport, radionuclide transport, and/or curvilinear coordinate system setup, the FLESCOT model, the FLOWER model, and Blumberg's model would be appropriate candidates for regional radionuclide modeling to predict the transport and dispersion of LLW disposed in the 2800-m and 3800-m sites. Although the RMA10 model does not incorporate a turbulence closure scheme, this model, with some modifications, is also an appropriate candidate for regional radionuclide modeling. FLESCOT is currently the only one that solves distributions of flow, turbulence, salinity, water temperature, sediments, dissolved contaminants, and sediment-sorbed contaminants. Thus, the FLESCOT model is recommended to be applied to the 2800-m and 3800-m sites to predict the transport and accumulation of LLW on a regional scale

Alternative Concept to Enhance the Disposal Efficiency for CANDU Spent Fuel Disposal System

International Nuclear Information System (INIS)

Lee, Jong Youl; Cho, Dong Geun; Kook, Dong Hak; Lee, Min Soo; Choi, Heui Joo

2011-01-01

There are two types of nuclear reactors in Korea and they are PWR type and CANDU type. The safe management of the spent fuels from these reactors is very important factor to maintain the sustainable energy supply with nuclear power plant. In Korea, a reference disposal system for the spent fuels has been developed through a study on the direct disposal of the PWR and CANDU spent fuel. Recently, the research on the demonstration and the efficiency analyses of the disposal system has been performed to make the disposal system safer and more economic. PWR spent fuels which include a lot of reusable material can be considered being recycled and a study on the disposal of HLW from this recycling process is being performed. CANDU spent fuels are considered being disposed of directly in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System (KRS) which was to dispose of both PWR type and CANDU type, the more effective CANDU spent fuel disposal systems were developed. To do this, the disposal canister for CANDU spent fuels was modified to hold the storage basket for 60 bundles which is used in nuclear power plant. With these modified disposal canister concepts, the disposal concepts to meet the thermal requirement that the temperature of the buffer materials should not be over 100 .deg. C were developed. These disposal concepts were reviewed and analyzed in terms of disposal effective factors which were thermal effectiveness, U-density, disposal area, excavation volume, material volume etc. and the most effective concept was proposed. The results of this study will be used in the development of various wastes disposal system together with the HLW wastes from the PWR spent fuel recycling process.

Site selection experience for a new low-level radioactive waste storage/disposal facility at the Savannah River Plant

International Nuclear Information System (INIS)

Towler, O.A.; Cook, J.R.; Helton, B.D.

1985-10-01

Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identified at SRP. The potential site were ranked based on how well they met a set of characteristics considered important in site selection for a low-level radioactive waste disposal facility. The characteristics were given a weighting factor representing its relative importance in meeting site performance criteria. A candidate site was selected and will be the subject of a site characterization program

Galvanic corrosion of lead coupled with titanium for nuclear fuel waste disposal

International Nuclear Information System (INIS)

Mani Mathew, P.; Krueger, P.A.

1989-01-01

In the Canadian Nuclear Fuel Waste Management Program, metals and alloys with low melting points are being evaluated for their potential application as cast matrices within used-fuel immobilization containers. This paper describes studies of galvanic corrosion between lead, candidate matrix metal and ASTM Grade-2 titanium, a candidate container-shell material. The studies were conducted under conditions that simulate a breached disposal container surrounded by a bentonite/sand mixture and emplaced in a granitic rock formation at a depth of 500-1000 m. The fractional factorial statistical design of Box Behnken was used in the tests, which covered a wide range of potential conditions that could occur in a nuclear-waste disposal vault. Test temperatures ranged from 293 to 423 K. Ionic strength and oxygen content of the simulated groundwater varied from 0.0015 to 1.37 mol and 0.02 to 8.0 mg/l, respectively. A mathematical expression was derived for the lead corrosion rates as a function of the independent variables: temperature, ionic strength, and oxygen content. This expression was used to calculate the lifetime of the additional barrier that a 25-mm thick lead layer could provide to a titanium container that eventually perforates by erosion. The results show that at least 860 years of additional barrier life could be provided by the lead matrix

Low level waste disposal

International Nuclear Information System (INIS)

Barthoux, A.

1985-01-01

Final disposal of low level wastes has been carried out for 15 years on the shallow land disposal of the Manche in the north west of France. Final participant in the nuclear energy cycle, ANDRA has set up a new waste management system from the production center (organization of the waste collection) to the disposal site including the setting up of a transport network, the development of assessment, additional conditioning, interim storage, the management of the disposal center, records of the location and characteristics of the disposed wastes, site selection surveys for future disposals and a public information Department. 80 000 waste packages representing a volume of 20 000 m 3 are thus managed and disposed of each year on the shallow land disposal. The disposal of low level wastes is carried out according to their category and activity level: - in tumuli for very low level wastes, - in monoliths, a concrete structure, of the packaging does not provide enough protection against radioactivity [fr

Waste disposal

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Verstricht, J.; Van Iseghem, P.; Buyens, M.

1998-01-01

The primary mission of the Waste Disposal programme at the Belgian Nuclear Research Centre SCK/CEN is to propose, develop, and assess solutions for the safe disposal of radioactive waste. In Belgium, deep geological burial in clay is the primary option for the disposal of High-Level Waste and spent nuclear fuel. The main achievements during 1997 in the following domains are described: performance assessment, characterization of the geosphere, characterization of the waste, migration processes, underground infrastructure

Space transportation and destination considerations for extraterrestrial disposal of radioactive waste

Science.gov (United States)

Zimmerman, A. V.; Thompson, R. L.; Lubick, R. J.

1973-01-01

A feasibility study is summarized of extraterrestrial (space) disposal of radioactive waste. The initial work on the evaluation and comparison of possible space destinations and launch vehicles is reported. Only current or planned space transportation systems were considered. The currently planned space shuttle was found to be more cost effective than current expendable launch vehicles, by about a factor of two. The space shuttle will require a third stage to perform the disposal missions. Depending on the particular mission this could be either a reusable space tug or an expendable stage such as a Centaur. Of the destinations considered, high earth orbits (between geostationary and lunar orbit altitudes), solar orbits (such as a 0.90 AU circular solar orbit) or a direct injection to solar system escape appear to be the best candidates. Both earth orbits and solar orbits have uncertainties regarding orbit stability and waste package integrity for times on the order of a million years.

Hybrid disposal systems and nitrogen removal in individual sewage disposal systems

Energy Technology Data Exchange (ETDEWEB)

Franks, A.L.

1993-06-01

The use of individual disposal systems in ground-water basins that have adverse salt balance conditions and/or geologically unsuitable locations, has become a major problem in many areas of the world. There has been much research in design of systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of the treated waste in areas with adverse geologic conditions and systems for the removal of nitrogen and phosphorus prior to percolation to the ground water. This paper outlines the history of development and rationale for design and construction of individual sewage disposal systems and describes the designs and limitations of the hybrid and denitrification units. The disposal systems described include Mounds, Evapotranspiration and Evapotranspiration/Infiltration systems. The denitrification units include those using methanol, sulfur and limestone, gray water and secondary treated wastewater for energy sources.

The disposal of orphan wastes using the greater confinement disposal concept

International Nuclear Information System (INIS)

Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H.; Dickman, P.T.

1991-01-01

In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ''home'' for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ''special-case'' or ''orphan'' wastes. This paper describes an ongoing project sponsored by the DOE's Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs

Salt disposal: Paradox Basin, Utah

International Nuclear Information System (INIS)

1983-04-01

This report presents the findings of a study conducted for the National Waste Terminal Storage (NWTS) Program. Permanent disposal options are examined for salt resulting from the excavation of a waste repository in the bedded salt deposits of the Paradox Basin of southeastern Utah. The study is based on a repository salt backfill compaction of 60% of the original density which leaves a total of 8 million tons of 95% pure salt to be disposed of over a 30-year period. The feasibility, impacts, and mitigation methods are examined for five options: commercial disposal, permanent onsite surface disposal, permanent offsite disposal, deepwell injection, and ocean and Great Salt Lake disposal. The study concludes the following: Commercial marketing of all repository salt would require a subsidy for transportation to major salt markets. Permanent onsite surface storage is both economically and technically feasible. Permanent offsite disposal is technically feasible but would incur additional transportation costs. Selection of an offsite location would provide a means of mitigating impacts associated with surface storage at the repository site. Deepwell injection is an attractive disposal method; however, the large water requirement, high cost of development, and poor performance of similar operating brine disposal wells eliminates this option from consideration as the primary means of disposal for the Paradox Basin. Ocean disposal is expensive because of high transportation cost. Also, regulatory approval is unlikely. Ocean disposal should be eliminated from further consideration in the Paradox Basin. Great Salt Lake disposal appears to be technically feasible. Great Salt Lake disposal would require state approval and would incur substantial costs for salt transportation. Permanent onsite disposal is the least expensive method for disposal of all repository salt

Proposal of a SiC disposal canister for very deep borehole disposal

Energy Technology Data Exchange (ETDEWEB)

Choi, Heui-Joo; Lee, Minsoo; Lee, Jong-Youl; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this paper authors proposed a silicon carbide, SiC, disposal canister for the DBD concept in Korea. A. Kerber et al. first proposed the SiC canister for a geological disposal of HLW, CANDU or HTR spent nuclear fuels. SiC has some drawbacks in welding or manufacturing a large canister. Thus, we designed a double layered disposal canister consisting of a stainless steel outer layer and a SiC inner layer. KAERI has been interested in developing a very deep borehole disposal (DBD) of HLW generated from pyroprocessing of PWR spent nuclear fuel and supported the relevant R and D with very limited its own budget. KAERI team reviewed the DBD concept proposed by Sandia National Laboratories (SNL) and developed its own concept. The SNL concept was based on the steel disposal canister. The authors developed a new technology called cold spray coating method to manufacture a copper-cast iron disposal canister for a geological disposal of high level waste in Korea. With this method, 8 mm thin copper canister with 400 mm in diameter and 1200 mm in height was made. In general, they do not give any credit on the lifetime of a disposal canister in DBD concept unlike the geological disposal. In such case, the expensive copper canister should be replaced with another one. We designed a disposal canister using SiC for DBD. According to an experience in manufacturing a small size canister, the fabrication of a large-size one is a challenge. Also, welding of SiC canister is not easy. Several pathways are being paved to overcome it.

Research on geological disposal: R and D concept on geological disposal

International Nuclear Information System (INIS)

1993-01-01

The objective on geological disposal of high-level radioactive wastes are to ensure the long term radiological protection of the human and his environment in accordance with current internationally agreed radiation protection principles. The principle of geological disposal is to settle the high-level wastes in deep underground so as to isolate them from the human and his environment considering the existence of groundwater. Japan is currently in the stage of assessing technical feasibility of geological disposal to the extent practicable. In accordance with the AEC (Atomic Energy Commission) policy in 1989, PNC (Power Reactor and Nuclear Fuel Development Corporation) has conducted the research and development on geological disposal in three areas: 1) studies of geological environment, 2) research and development of disposal technology, and 3) performance assessment study. (author)

Cosmic disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Inoue, Y; Morisawa, S [Kyoto Univ. (Japan). Faculty of Engineering

1975-03-01

The technical and economical possibility and safety of the disposal of highly radioactive waste into cosmos are reviewed. The disposal of highly radioactive waste is serious problem to be solved in the near future, because it is produced in large amounts by the reprocessing of spent fuel. The promising methods proposed are (i) underground disposal, (ii) ocean disposal, (iii) cosmic disposal and (iv) extinguishing disposal. The final disposal method is not yet decided internationally. The radioactive waste contains very long life nuclides, for example transuranic elements and actinide elements. The author thinks the most perfect and safe disposal method for these very long life nuclides is the disposal into cosmos. The space vehicle carrying radioactive waste will be launched safely into outer space with recent space technology. The selection of orbit for vehicles (earth satellite or orbit around planets) or escape from solar system, selection of launching rocket type pretreatment of waste, launching weight, and the cost of cosmic disposal were investigated roughly and quantitatively. Safety problem of cosmic disposal should be examined from the reliable safety study data in the future.

History of geological disposal concept (3). Implementation phase of geological disposal (2000 upward)

International Nuclear Information System (INIS)

Masuda, Sumio; Sakuma, Hideki; Umeki, Hiroyuki

2015-01-01

Important standards and concept about geological disposal have been arranged as an international common base and are being generalized. The authors overview the concept of geological disposal, and would like this paper to help arouse broad discussions for promoting the implementation plan of geological disposal projects in the future. In recent years, the scientific and technological rationality of geological disposal has been recognized internationally. With the addition of discussions from social viewpoints such as ethics, economy, etc., geological disposal projects are in the stage of starting after establishment of social consensus. As an international common base, the following consolidated and systematized items have been presented as indispensable elements in promoting business projects: (1) step-by-step approach, (2) safety case, (3) reversibility and recovery potential, and (4) trust building and communications. This paper outlines the contents of the following cases, where international common base was reflected on the geological disposal projects in Japan: (1) final disposal method and safety regulations, and (2) impact of the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Station accident on geological disposal plan. (A.O.)

Risk assessment of natural disasters in the course of selection of nuclear waste disposal

International Nuclear Information System (INIS)

Wu Weicheng; Ai Guigen

1995-01-01

Natural disasters are calamities which bring about enormous damage to human beings and their accommodations and equipment. Based on the research of disaster risk and example study of volcanism, we tried to carry out the risk assessment of natural disasters which potentially occur in the candidate area of nuclear waste disposal by three steps of analyses, defining the most frequent occurring area of disasters, determining the parameters of risk assessment and dividing the most dangerous site and risk grades

Ocean Disposal Site Monitoring

Science.gov (United States)

EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

Geological disposal of radioactive wastes

International Nuclear Information System (INIS)

Sato, Tsutomu

2000-01-01

For disposing method of radioactive wastes, various feasibilities are investigated at every nations and international organizations using atomic energy, various methods such as disposal to cosmic space, disposal to ice sheet at the South Pole and so forth, disposal into ocean bed or its sediments, and disposal into ground have been examined. It is, however, impossible institutionally at present, to have large risk on accident in the disposal to cosmic space, to be prohibited by the South Pole Treaty on the disposal to ice sheet at the South Pole, and to be prohibited by the treaty on prevention of oceanic pollution due to the disposal of wastes and so forth on the disposal into oceanic bed or its sediments (London Treaty). Against them, the ground disposal is thought to be the most powerful method internationally from some reasons shown as follows: no burden to the next generation because of no need in long-term management by human beings; safety based on scientific forecasting; disposal in own nation; application of accumulated technologies on present mining industries, civil engineering, and so forth to construction of a disposal facility; and, possibility to take out wastes again, if required. For the ground disposal, wastes must be buried into the ground and evaluated their safety for long terms. It is a big subject to be taken initiative by engineers on geoscience who have quantified some phenomena in the ground and at ultra long term. (G.K.)

Disposal of Radioactive Waste

International Nuclear Information System (INIS)

2011-01-01

This Safety Requirements publication applies to the disposal of radioactive waste of all types by means of emplacement in designed disposal facilities, subject to the necessary limitations and controls being placed on the disposal of the waste and on the development, operation and closure of facilities. The classification of radioactive waste is discussed. This Safety Requirements publication establishes requirements to provide assurance of the radiation safety of the disposal of radioactive waste, in the operation of a disposal facility and especially after its closure. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. This is achieved by setting requirements on the site selection and evaluation and design of a disposal facility, and on its construction, operation and closure, including organizational and regulatory requirements.

Development, evaluation, and selection of candidate high-level waste forms

International Nuclear Information System (INIS)

Bernadzikowski, T.A.; Allender, J.S.; Gordon, D.E.; Gould, T.H. Jr.

1982-01-01

The seven candidate waste forms, evaluated as potential media for the immobilization and gelogic disposal of high-level nuclear wastes were borosilicate glass, SYNROC, tailored ceramic, high-silica glass, FUETAP concrete, coated sol-gel particles, and glass marbles in a lead matrix. The evaluation, completed on August 1, 1981, combined preliminary waste form evaluations conducted at Department of Energy (DOE) defense waste-sites and at independent laboratories, peer review assessments, a product performance evaluation, and a processability analysis. Based on the combined results of these four inputs, two of the seven forms, borosilicate glass and a titanate-based ceramic, SYNROC, were selected as the reference and alternative forms, respectively, for continued development and evaluation in the National HLW Program. The borosilicate glass and ceramic forms were further compared during FY-1982 on the basis of risk assessments, cost comparisons, properties comparisons, and conformance with proposed regulatory and repository criteria. Both the glass and ceramic forms are viable candidates for use at DOE defense HLW sites; they are also candidates for immobilization of commercial reprocessing wastes. This paper describes the waste form screening process, discusses each of the four major inputs considered in the selection of the two forms in 1981, and presents a brief summary of the comparisons of the two forms during 1982 and the selection process to determine the final form for SRP defense HLW

Ecological survey for the siting of the Mixed and Low-Level Waste Disposal Facility

International Nuclear Information System (INIS)

Hoskinson, R.L.

1994-05-01

This report summarizes the results of field ecological surveys conducted by the Center for Integrated Environmental Technologies (CIET) on the Idaho National Engineering Lab. (INEL) at two candidate locations for the siting of the Mixed and Low-Level Waste Disposal Facility (MLLWDF). The purpose of these surveys was to comply with all Federal laws and Executive Orders to identify and evaluate any potential environmental impacts because of the project. The boundaries of the candidate locations were marked with blaze-orange lath survey marker stakes by the project management. Global Positioning in System (GPS) measurements of the marker stakes were made, and input to the Arc/Info geographic information system (GIS). Field surveys were conducted to assess any potential impact to any important species, important habitats, and to any environmental study areas. The GIS location data were overlayed onto the INEL vegetation map and an analysis of vegetation classes on the locations was done. Two species of rare vascular plants have previously been reported to occur in the vicinity of the candidate locations. Two C2 species, the ferruginous hawk (Buteo regalis) and the loggerhead shrike (Lanius ludovicianus) would also be expected to frequent the candidate locations. No significant ecological impact is anticipated if the MLLWDF were constructed on either candidate location. However, both candidate locations are in the central area of the INEL where there is minimal disturbance to the ecosystem by facilities or humans

Waste disposal: preliminary studies

International Nuclear Information System (INIS)

Carvalho, J.F. de.

1983-01-01

The problem of high level radioactive waste disposal is analyzed, suggesting an alternative for the final waste disposal from irradiated fuel elements. A methodology for determining the temperature field around an underground disposal facility is presented. (E.G.) [pt

Geomorphologic characteristic of low-intermediate level radioactive waste disposal land candidate at Lemahabang area

International Nuclear Information System (INIS)

Sucipta

1998-01-01

Geomorphological aspect is a factor should be considered on land evaluation for radioactive wastes disposal purpose. The aspect is important because geomorphological factors contribute on hydrological and erosion condition of the land. The objective of the study is to characterize the geomorphological condition of the land, i.e. land form, geomorphological processes, rock type, soil, surface water, ground water, vegetation and land use. The study was conducted by descriptive analyses from literature study and field geomorphological method, with evaluation as well as developed for terrain analyses. The study area can be divided industry for land from units, I.e. tuff undulating unit (land use: plantation), coastal deposits plain unit, silty sand fluvial plain unit (land use: wet rice field) and unconsolidated sand beach deposits plain unit (opened land without vegetation). Hydrologically, the study area can be divided indus tri three small river stream area (RSA). Detailed description of geomorfological condition is showed by table and geomorphological map. (author)

Site characterization quality assurance for the California LLRW Disposal Site Project

International Nuclear Information System (INIS)

Hanrahan, T.P.; Ench, J.E.; Serlin, C.L.; Bennett, C.B.

1988-01-01

In December of 1985 US Ecology was chosen as the license designee for the State of California's low-level radioactive waste disposal facility. In early 1987, three candidate sites were selected for characterization studies in preparation for identifying the preferred site. The geotechnical characterization activities along with studies of the ecological and archaeological attributes, as well as assessments of the socio-economic impacts and cultural resources all provide input towards selection of the proposed site. These technical studies in conjunction with comments from local citizen committees and other interested parties are used as a basis for determining the proposed site for which full site characterization as required by California licensing requirements are undertaken. The purpose of this paper is to present an overview of the program for Quality Assurance and Quality Control for the site characterization activities on the California LLRW Disposal Site Project. The focus is on three major perspectives: The composite QA Program and two of the primary characterization activities, the geotechnical and the meteorological investigations

Evaluation of Proposed New LLW Disposal Activity: Disposal of Aqueous PUREX Waste Stream in the Saltstone Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.

2003-01-01

The Aqueous PUREX waste stream from Tanks 33 and 35, which have been blended in Tank 34, has been identified for possible processing through the Saltstone Processing Facility for disposal in the Saltstone Disposal Facility

Corrosion considerations of high-nickel alloys and titanium alloys for high-level radioactive waste disposal containers

International Nuclear Information System (INIS)

Gdowski, G.E.; McCright, R.D.

1991-07-01

Corrosion resistant materials are being considered for the metallic barrier of the Yucca Mountain Project's high-level radioactive waste disposal containers. High nickel alloys and titanium alloys have good corrosion resistance properties and are considered good candidates for the metallic barrier. The localized corrosion phenomena, pitting and crevice corrosion, are considered as potentially limiting for the barrier lifetime. An understanding of the mechanisms of localized corrosion of how various parameters affect it will be necessary for adequate performance assessments of candidate container materials. Examples of some of the concerns involving candidate container materials. Examples of some of the concerns of involving localized corrosion are discussed. The effects of various parameters, such as temperature and concentration of halide species, on localized corrosion are given. In addition concerns about aging of the protective oxide layer in the expected service temperature range (50 to 250 degrees C) are presented. Also some mechanistic considerations of localized corrosion are given. 31 refs., 1 tab

Underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-08-15

Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

Alternative disposal technologies for new low-level radioactive waste disposal/storage facilities at the Savannah River Plant

International Nuclear Information System (INIS)

Cook, J.R.

1987-01-01

A Draft Environmental Impact Statement for Waste Management Activities for groundwater protection has been prepared for the Savannah River Plant. Support documentation for the DEIS included an Environmental Information Document on new radioactive waste disposal and storage facilities in which possible alternative disposal technologies were examined in depth. Six technologies that would meet the needs of the Savannah River Plant that selected for description and analysis include near surface disposal, near surface disposal with exceptions, engineered storage, engineered disposal, vault disposal of untreated waste, and a combination of near surface disposal, engineered disposal, and engineered storage. 2 refs

Safety assessment of spent fuel disposal in Haestholmen, Kivetty, Olkiluoto and Romuvaara - TILA-99

Energy Technology Data Exchange (ETDEWEB)

Vieno, T.; Nordman, H. [VTT Energy (Finland)

1999-03-01

The spent fuel from the Finnish nuclear power plants is planned to be disposed of in copper-iron canisters emplaced in a KBS-3 type repository constructed at a depth of about 500 metres at one of the four candidate sites investigated. The disposal concept aims at long-term isolation of the spent fuel assemblies from the biosphere and even from the geosphere. The evaluation of the normal evolution of the disposal system accords with the conclusions of the previous Finnish, Swedish and Canadian safety assessments of similar disposal concepts. Subject to the influence of the expected, normal evolution of the repository, initially intact copper-iron canisters will most likely preserve their integrity for more than one million years at any of the candidate sites. Consequently, the best-estimate assessment is that there never will be any significant releases of radionuclides from the repository into the geosphere. Consequences of potential canister failures have been evaluated using conservative assumptions, models and data. The results show that at any of the sites a large number of canisters could be assumed to be initially defective or to `disappear` simultaneously after some time without that the proposed constraints for release rates into the biosphere or dose rates were exceeded. In most cases this conclusion is valid for all canisters failing simultaneously, even if rather pessimistic flow and transport data is used. In the sensitivity and `what if` analyses where very high flow rates of saline groundwater are assumed, highest release and dose rates are caused by weakly-sorbing cations Sr-90 and Ra-226. The most important differences between the sites are related to the coastal location and brackish/saline groundwater of Haestholmen and Olkiluoto, and on the other hand to the inland location and fresh groundwater of Kivetty and Romuvaara. Because of the ongoing postglacial land uplift at the coast of the Baltic Sea, Olkiluoto and Haestholmen, too, may become

Safety assessment of spent fuel disposal in Haestholmen, Kivetty, Olkiluoto and Romuvaara - TILA-99

International Nuclear Information System (INIS)

Vieno, T.; Nordman, H.

1999-03-01

The spent fuel from the Finnish nuclear power plants is planned to be disposed of in copper-iron canisters emplaced in a KBS-3 type repository constructed at a depth of about 500 metres at one of the four candidate sites investigated. The disposal concept aims at long-term isolation of the spent fuel assemblies from the biosphere and even from the geosphere. The evaluation of the normal evolution of the disposal system accords with the conclusions of the previous Finnish, Swedish and Canadian safety assessments of similar disposal concepts. Subject to the influence of the expected, normal evolution of the repository, initially intact copper-iron canisters will most likely preserve their integrity for more than one million years at any of the candidate sites. Consequently, the best-estimate assessment is that there never will be any significant releases of radionuclides from the repository into the geosphere. Consequences of potential canister failures have been evaluated using conservative assumptions, models and data. The results show that at any of the sites a large number of canisters could be assumed to be initially defective or to 'disappear' simultaneously after some time without that the proposed constraints for release rates into the biosphere or dose rates were exceeded. In most cases this conclusion is valid for all canisters failing simultaneously, even if rather pessimistic flow and transport data is used. In the sensitivity and 'what if' analyses where very high flow rates of saline groundwater are assumed, highest release and dose rates are caused by weakly-sorbing cations Sr-90 and Ra-226. The most important differences between the sites are related to the coastal location and brackish/saline groundwater of Haestholmen and Olkiluoto, and on the other hand to the inland location and fresh groundwater of Kivetty and Romuvaara. Because of the ongoing postglacial land uplift at the coast of the Baltic Sea, Olkiluoto and Haestholmen, too, may become

Low-level radioactive mixed waste land disposal facility -- Permanent disposal

International Nuclear Information System (INIS)

Erpenbeck, E.G.; Jasen, W.G.

1993-03-01

Radioactive mixed waste (RMW) disposal at US Department of Energy (DOE) facilities is subject to the Resource Conservation and Recovery Act of 1976 (RCRA) and the Hazardous and Solid Waste Amendments of 1984 (HSWA). Westinghouse Hanford Company, in Richland, Washington, has completed the design of a radioactive mixed waste land disposal facility, which is based on the best available technology compliant with RCRA. When completed, this facility will provide permanent disposal of solid RMW, after treatment, in accordance with the Land Disposal Restrictions. The facility includes a double clay and geosynthetic liner with a leachate collection system to minimize potential leakage of radioactive or hazardous constituents from the landfill. The two clay liners will be capable of achieving a permeability of less than 1 x 10 -7 cm/s. The two clay liners, along with the two high density polyethylene (HDPE) liners and the leachate collection and removal system, provide a more than conservative, physical containment of any potential radioactive and/or hazardous contamination

Determining the Suitability of Materials for Disposal at Sea under the London Convention 1972 and London Protocol 1996: A Radiological Assessment Procedure. 2015 Edition

International Nuclear Information System (INIS)

2015-01-01

This publication provides guidance on performing specific assessments of candidate materials for dumping at sea, to determine whether the materials are de minimis in the meaning of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter 1972 (the London Convention 1972) and the related Protocol 1996 (the London Protocol 1996). It presents a detailed radiological procedure to assess doses to workers and members of the public and doses to marine flora and fauna related to the dumping of materials at sea. The procedures in this publication follow the requirements to protect the environment in the IAEA Safety Standards and in the recommendations by the International Commission of Radiological Protection. It is expected to be used by national regulatory authorities responsible for authorizing disposal at sea of candidate materials as well as by those companies and individuals applying to obtain permission to dispose these materials at sea

Uncertainties about the safety of disposal leading to a wish to keep alternatives open. Discussion on the concepts 'storage' ('wait and see') vs. 'disposal' and 'retrievable disposal' vs. 'definitive disposal'

International Nuclear Information System (INIS)

Norrby, S.

2000-01-01

Uncertainties about the safety of final disposal may lead to unwillingness to take decisions about waste management issues that may seem to be non-reversible. This has lead to proposals that we should wait with decisions on final measures and instead store the waste for some period of time. Also the possibility of retrieval may lead to decisions not to go for permanent disposal but instead to retrievable disposal. These aspects and the pros and cons are discussed both from a more general perspective and also with some reflections from the Swedish programme for nuclear waste management and disposal. (author)

Personality predictors of mortality in cardiac transplant candidates and recipients.

Science.gov (United States)

Brandwin, M; Trask, P C; Schwartz, S M; Clifford, M

2000-08-01

Emotional factors are generally recognized as impacting the care of end-stage heart disease and mortality following cardiac transplants. Equally important, however, are predictors of pretransplant mortality. The current study examined the utility of the Millon Behavioral Health Inventory (MBHI) as a predictor of pre- and posttransplant mortality. A total of 103 cardiac transplant candidates were assessed with the MBHI as part of a pretransplant evaluation that included baseline demographic variables and cardiac status. Time to transplant and mortality status at 1 and 5 years was also obtained. Cluster analysis of MBHI response scores elicited two clusters characterized by high and low distress. Cluster membership predicted survival status at 1-year and 5-year follow-up, with high distress cluster patients having significantly higher mortality in both the total sample and a subgroup of patients who did receive a heart transplant. These results support the value of the MBHI for assessing personality attributes that may dispose toward unfavorable outcome in heart transplant candidates. Further understanding of psychosocial contributions to illness course and outcome may enable more effective selection of treatment interventions with cardiac patients.

Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

Energy Technology Data Exchange (ETDEWEB)

Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

2013-07-29

Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

Alternative approaches to assessing the performance and suitability of Yucca Mountain for spent fuel disposal. Final report

International Nuclear Information System (INIS)

McGuire, R.; Smith, G.; Klos, R.

1998-11-01

Significant resources and effort have been expended by EPRI over the past few years in modeling and understanding issues related to high-level radioactive waste disposal. Previous reports have documented the general model used in the EPRI work and specific inputs to that model for examination of the potential repository at Yucca Mountain, Nevada. Modeling of the potential Yucca Mountain site is an on-going process, and new data are being collected with which to evaluate and modify models of physical processes. This report is divided into two parts. The first part presents results from specific calculational cases of repository performance, updated for the most recent data and conceptual models. The second part discusses possible alternatives for the components of the assessment context for a repository at Yucca Mountain. Part 2 also presents additional information on time frames and a interaction matrix method of documenting TSPA model interactions. The main purposes of Part of this report is to describe the subsystem and total system performance models and present results and analysis of the results. Part 1 includes presentation of new models of waste container failure that accounts for new container material, a new model of the effect of hydrothermal activity and heterogeneous groundwater flow in the unsaturated zone on temperatures and the distribution of groundwater capable of dripping into the repository drifts. Part 1 also: identifies the key technical components of the candidate spent fuel and HLW disposal facility at Yucca Mountain using IMARC Phase 4; makes recommendations regarding the prioritization of the technical development work remaining; and provides an assessment of the overall technical suitability of the candidate HLW disposal facility at Yucca Mountain

Toxic and hazardous waste disposal. Volume 4. New and promising ultimate disposal options

International Nuclear Information System (INIS)

Pojasek, R.B.

1980-01-01

Separate abstrats were prepared for four of the eighteen chapters of this book which reviews several disposal options available to the generators of hazardous wastes. The chapters not abstracted deal with land disposal of hazardous wastes, the solidification/fixation processes, waste disposal by incineration and molten salt combustion and the use of stabilized industrial waste for land reclamation and land farming

Disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-01-15

The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

Report on radioactive waste disposal

International Nuclear Information System (INIS)

1993-01-01

The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

Korean Reference HLW Disposal System

Energy Technology Data Exchange (ETDEWEB)

Choi, Heui Joo; Lee, J. Y.; Kim, S. S. (and others)

2008-03-15

This report outlines the results related to the development of Korean Reference Disposal System for High-level radioactive wastes. The research has been supported around for 10 years through a long-term research plan by MOST. The reference disposal method was selected via the first stage of the research during which the technical guidelines for the geological disposal of HLW were determined too. At the second stage of the research, the conceptual design of the reference disposal system was made. For this purpose the characteristics of the reference spent fuels from PWR and CANDU reactors were specified, and the material and specifications of the canisters were determined in term of structural analysis and manufacturing capability in Korea. Also, the mechanical and chemical characteristics of the domestic Ca-bentonite were analyzed in order to supply the basic design parameters of the buffer. Based on these parameters the thermal and mechanical analysis of the near-field was carried out. Thermal-Hydraulic-Mechanical behavior of the disposal system was analyzed. The reference disposal system was proposed through the second year research. At the final third stage of the research, the Korean Reference disposal System including the engineered barrier, surface facilities, and underground facilities was proposed through the performance analysis of the disposal system.

Disposal options for radioactive waste

International Nuclear Information System (INIS)

Olivier, J.P.

1991-01-01

On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

Underground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

International Nuclear Information System (INIS)

2003-12-01

Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

International Nuclear Information System (INIS)

Romano, Stephen; Welling, Steven; Bell, Simon

2003-01-01

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

International Nuclear Information System (INIS)

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

1982-08-01

An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables

Behaviour of a clay layer submitted to bending: application to a landfill for storing very low level radioactive waste

International Nuclear Information System (INIS)

Camp Devernay, S.

2008-12-01

The sealing cover system of landfills for storing non bio-degradable and dangerous waste is most of the time made up of a layer of clay and/or a geo-membrane. The question of the optimization of the conditions of storage of the radioactive waste envisage a surface storage for very low level radioactive waste (VLLW) and low and intermediate short-lived radioactive waste. This study is applied to a VLLW disposal facility of which the cover is made up of a clay layer over a geo-membrane but can be transposed to landfill for dangerous waste. The cover clay barrier of a landfill must preserve its properties; in particular its permeability must remain inferior to ten to the minus nine meters per second, during the life of the landfill in spite of the various solicitations which can generate cracking. Among these solicitations, the relative settlements of subjacent waste, generating bending solicitation, are one of the most critical solicitations. The current regulation concerning the implementation as a cover of a clay layer presents gaps, in particular with regard to the deformability of clay. This study presents the interest to couple laboratory tests (four points bending tests, splitting test and punching test) with field bending tests carried out at scale one and with their modeling with centrifugal tests. These tests were also numerically modeled by finite elements. A good compatibility of the results, in particular with regard to the definition of the conditions of initiation of the crack by bending, is shown. Numerical modeling and centrifugal tests made it possible to extend the study to unperformed in situ cases (settlement tests, reinforcement of the clay). (author)

Nuclear fuel waste disposal

International Nuclear Information System (INIS)

Allan, C.J.

1993-01-01

The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

Study of extraterrestrial disposal of radioactive wastes. Part 2: Preliminary feasibility screening study of extraterrestrial disposal of radioactive wastes in concentrations, matrix materials, and containers designed for storage on earth

Science.gov (United States)

Hyland, R. E.; Wohl, M. L.; Thompson, R. L.; Finnegan, P. M.

1972-01-01

The results are reported of a preliminary feasibility screening study for providing long-term solutions to the problems of handling and managing radioactive wastes by extraterrestrial transportation of the wastes. Matrix materials and containers are discussed along with payloads, costs, and destinations for candidate space vehicles. The conclusions reached are: (1) Matrix material such as spray melt can be used without exceeding temperature limits of the matrix. (2) The cost in mills per kw hr electric, of space disposal of fission products is 4, 5, and 28 mills per kw hr for earth escape, solar orbit, and solar escape, respectively. (3) A major factor effecting cost is the earth storage time. Based on a normal operating condition design for solar escape, a storage time of more than sixty years is required to make the space disposal charge less than 10% of the bus-bar electric cost. (4) Based on a 10 year earth storage without further processing, the number of shuttle launches required would exceed one per day.

Chinese buffer material for high-level radiowaste disposal-basic features of GMZ-1

International Nuclear Information System (INIS)

Wen, Zhijian

2005-01-01

Radioactive wastes arising from a wide range of human activities are in many different physical and chemical forms, contaminated with varying radioactivity. Their common feature is the potential hazard associated with their radioactivity and the need to manage them in such a way as to protect the human environment. The geological disposal is regarded as the most reasonable and effective way to safety disposal high-level radioactive wastes in the world. The conceptual model of geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineered barrier system. The buffer is one of the main engineered barriers for HLW repository. The buffer material is expected to maintain its low water permeability, self-sealing property, radio nuclides adsorption and retardation property, thermal conductivity, chemical buffering property, overpack supporting property, stress buffering property over a long period of time. Bentonite is selected as the main content of buffer material that can satisfy above. GMZ deposit is selected as the candidate supplier for Chinese buffer material of High Level Radioactive waste repository. This paper presents geological features of GMZ deposit and basic property of GMZ Na bentonite. GMZ bentonite deposit is a super large scale deposits with high content of Montmorillonite (about 75%) and GMZ-1, which is Na-bentonite produced from GMZ deposit is selected as reference material for Chinese buffer material study

Waste-Mixes Study for space disposal

International Nuclear Information System (INIS)

McCallum, R.F.; Blair, H.T.; McKee, R.W.; Silviera, D.J.; Swanson, J.L.

1983-01-01

The Wastes Mixes Study is a component of Cy-1981 and 1982 research activities to determine if space disposal could be a feasible complement to geologic disposal for certain high-level (HLW) and transuranic wastes (TRU). The objectives of the study are: to determine if removal of radionuclides from HLW and TRU significantly reduces the long-term radiological risks of geologic disposal; to determine if chemical partitioning of the waste for space disposal is technically feasible; to identify acceptable waste forms for space disposal; and to compare improvements in geologic disposal system performance to impacts of additional treatment, storage, and transportation necessary for space disposal. To compare radiological effects, five system alternatives are defined: Reference case - All HLW and TRU to a repository. Alternative A - Iodine to space, the balance to a repository. Alternative B - Technetium to space, the balance to a repository. Alternative C - 95% of cesium and strontium to a repository; the balance of HLW aged first, then to space; plutonium separated from TRU for recycle; the balance of the TRU to a repository. Alternative D - HLW aged first, then to space, plutonium separated from TRU for recycle; the balance of the TRU to a repository. The conclusions of this study are: the incentive for space disposal is that it offers a perception of reduced risks rather than significant reduction. Suitable waste forms for space disposal are cermet for HLW, metallic technetium, and lead iodide. Space disposal of HLW appears to offer insignificant safety enhancements when compared to geologic disposal; the disposal of iodine and technetium wastes in space does not offer risk advantages. Increases in short-term doses for the alternatives are minimal; however, incremental costs of treating, storing and transporting wastes for space disposal are substantial

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Energy Technology Data Exchange (ETDEWEB)

Strum, M.J.; Weiss, H.; Farmer, J.C. (Lawrence Livermore National Lab., CA (USA)); Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-06-01

This volume surveys the effects of welding on the degradation modes of three austenitic alloys: Types 304L and 316L stainless steels and Alloy 825. These materials are candidates for the fabrication of containers for the long-term storage of high-level nuclear waste. The metallurgical characteristics of fusion welds are reviewed here and related to potential degradation modes of the containers. Three specific areas are discussed in depth: (1) decreased resistance to corrosion in the forms of preferential corrosion, sensitization, and susceptibility to stress corrosion cracking, (2) hot cracking in the heat-affected zone and the weld zone, and (3) formation of intermetallic phases. The austenitic alloys are ranked as follows in terms of overall weldability: Alloy 825 (best) > Type 316L stainless steel > Type 304L stainless steel (worst). 108 refs., 31 figs., 7 tabs.

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Strum, M.J.; Weiss, H.; Farmer, J.C.; Bullen, D.B.

1988-06-01

This volume surveys the effects of welding on the degradation modes of three austenitic alloys: Types 304L and 316L stainless steels and Alloy 825. These materials are candidates for the fabrication of containers for the long-term storage of high-level nuclear waste. The metallurgical characteristics of fusion welds are reviewed here and related to potential degradation modes of the containers. Three specific areas are discussed in depth: (1) decreased resistance to corrosion in the forms of preferential corrosion, sensitization, and susceptibility to stress corrosion cracking, (2) hot cracking in the heat-affected zone and the weld zone, and (3) formation of intermetallic phases. The austenitic alloys are ranked as follows in terms of overall weldability: Alloy 825 (best) > Type 316L stainless steel > Type 304L stainless steel (worst). 108 refs., 31 figs., 7 tabs

Treated Effluent Disposal Facility

Data.gov (United States)

Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

Unreviewed Disposal Question Evaluation: Waste Disposal in Engineered Trenches 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Butcher, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-12-12

Revision 0 of this UDQE addressed the proposal to place Engineered Trench #3 (ET#3) in the footprint designated for Slit Trench #12 (ST#12) and operate using ST#12 disposal limits. Similarly, Revision 1 evaluates whether ET#4 can be located in and operated to Slit Trench #13 (ST#13) disposal limits. Both evaluations conclude that the proposed operations result in an acceptably small risk of exceeding a SOF of 1.0 and approve these actions from a performance assessment (PA) perspective. Because ET#3 will be placed in the location previously designated for ST#12, Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore, new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

Geological disposal of nuclear waste

International Nuclear Information System (INIS)

1979-01-01

Fourteen papers dealing with disposal of high-level radioactive wastes are presented. These cover disposal in salt deposits, geologic deposits and marine disposal. Also included are papers on nuclear waste characterization, transport, waste processing technology, and safety analysis. All of these papers have been abstracted and indexed

The Suitable Geological Formations for Spent Fuel Disposal in Romania

International Nuclear Information System (INIS)

Marunteanu, C.; Ionita, G.; Durdun, I.

2007-01-01

Using the experience in the field of advanced countries and formerly Romanian program data, ANDRAD, the agency responsible for the disposal of radioactive wastes, started the program for spent fuel disposal in deep geological formations with a documentary analysis at the national scale. The potential geological formations properly characterized elsewhere in the world: salt, clay, volcanic tuff, granite and crystalline rocks,. are all present in Romania. Using general or specific selection criteria, we presently consider the following two areas for candidate geological formations: 1. Clay formations in two areas in the western part of Romania: (1) The Pannonian basin Socodor - Zarand, where the clay formation is 3000 m thick, with many bentonitic strata and undisturbed structure, and (2) The Eocene Red Clay on the Somes River, extending 1200 m below the surface. They both need a large investigation program in order to establish and select the required homogeneous, dry and undisturbed zones at a suitable depth. 2. Old platform green schist formations, low metamorphosed, quartz and feldspar rich rocks, in the Central Dobrogea structural unit, not far from Cernavoda NPP (30 km average distance), 3000 m thick and including many homogeneous, fine granular, undisturbed, up to 300 m thick layers. (authors)

The disposal of radioactive waste

International Nuclear Information System (INIS)

Ormai, P.

2006-01-01

The first part shows different ways of 'producing' radioactive wastes, defines the wastes of small, medium and high activity and gives estimation on the quantity of the necessary capacities of waste disposal facilities. The modern radioactive waste disposal that is the integrated processing of the form of waste, the package, the technical facility and the embedding geological environment that guarantee the isolation together. Another factor is the lifetime of radioactive waste which means that any waste containing long lifetime waste in higher concentration than 400-4000 kBq/kg should be disposed geologically. Today the centre of debate disposal of radioactive waste is more social than technical. For this reason not only geological conditions and technical preparations, but social discussions and accepting communities are needed in selecting place of facilities. Now, the focus is on long term temporary disposal of high activity wastes, like burnt out heating elements. The final part of the paper summarizes the current Hungarian situation of disposal of radioactive wastes. (T-R.A.)

Marine disposal of radioactive wastes - the debate

International Nuclear Information System (INIS)

Blair, I.

1985-01-01

The paper defends the case for marine disposal of radioactive wastes. The amount of packaged waste disposed; the site for marine disposal; the method of disposal; the radioactivity arising from the disposal; and safety factors; are all briefly discussed. (U.K.)

Design study on containers for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Arup, O.

1985-01-01

A study has been made of the requirements and design features for containers to isolate vitrified high-level radioactive waste from the environment for a period of 500 to 1000 years. The requirements for handling, storing and transporting containers have been identified following a study of disposal operations, and the pressures and temperatures which may possibly be experienced in clay, granite and salt formations have been estimated. A range of possible container designs have been proposed to satisfy the requirements of each of the disposal environments. Alternative design concepts in corrosion resistant or corrosion allowance material have been suggested. Some resist pressure by using a structural shell leaving the contents unstressed whereas others transmit loads to their contents. Potentially suitable container shell materials have been selected following a review of corrosion studies and although metals have not been specified in detail, titanium alloys and low carbon steels are thought to be appropriate for corrosion resistant and corrosion allowance designs respectively. Performance requirements for container filler materials have been identified and candidate materials assessed. However, no entirely suitable materials have been found and further research is required in this area. A preliminary container stress analysis has shown the importance of thermal modelling and that if lead is used as a filler it dominates the stress response of the container. Possible methods of manufacturing disposal containers have been assessed and found to be generally feasible although filling operations and container closure could be difficult

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

International Nuclear Information System (INIS)

Di Sanza, E.F.; Carilli, J.T.

2006-01-01

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers

Energy Technology Data Exchange (ETDEWEB)

Vinson, D.W.; Nutt, W.M.; Bullen, D.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States)

1995-06-01

Oxidation and atmospheric corrosion data suggest that addition of Cr provides the greatest improvement in oxidation resistance. Cr-bearing cast irons are resistant to chloride environments and solutions containing strongly oxidizing constituents. Weathering steels, including high content and at least 0.04% Cu, appear to provide adequate resistance to oxidation under temperate conditions. However, data from long-term, high-temperature oxidation studies on weathering steels were not available. From the literature, it appears that the low alloy steels, plain carbon steels, cast steels, and cast irons con-ode at similar rates in an aqueous environment. Alloys containing more than 12% Cr or 36% Ni corrode at a lower rate than plain carbon steels, but pitting may be worse. Short term tests indicate that an alloy of 9Cr-1Mo may result in increased corrosion resistance, however long term data are not available. Austenitic cast irons show the best corrosion resistance. A ranking of total corrosion performance of the materials from most corrosion resistant to least corrosion resistant is: Austenitic Cast Iron; 12% Cr = 36% Ni = 9Cr-1Mo; Carbon Steel = Low Alloy Steels; and Cast Iron. Since the materials to be employed in the Advanced Conceptual Design (ACD) waste package are considered to be corrosion allowance materials, the austenitic cast irons, high Cr steels, high Ni steels and the high Cr-Mo steels should not be considered as candidates for the outer containment barrier. Based upon the oxidation and corrosion data available for carbon steels, low alloy steels, and cast irons, a suitable list of candidate materials for a corrosion allowance outer barrier for an ACD waste package could include, A516, 2.25%Cr -- 1%Mo Steel, and A27.

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers

International Nuclear Information System (INIS)

Vinson, D.W.; Nutt, W.M.; Bullen, D.B.

1995-06-01

Oxidation and atmospheric corrosion data suggest that addition of Cr provides the greatest improvement in oxidation resistance. Cr-bearing cast irons are resistant to chloride environments and solutions containing strongly oxidizing constituents. Weathering steels, including high content and at least 0.04% Cu, appear to provide adequate resistance to oxidation under temperate conditions. However, data from long-term, high-temperature oxidation studies on weathering steels were not available. From the literature, it appears that the low alloy steels, plain carbon steels, cast steels, and cast irons con-ode at similar rates in an aqueous environment. Alloys containing more than 12% Cr or 36% Ni corrode at a lower rate than plain carbon steels, but pitting may be worse. Short term tests indicate that an alloy of 9Cr-1Mo may result in increased corrosion resistance, however long term data are not available. Austenitic cast irons show the best corrosion resistance. A ranking of total corrosion performance of the materials from most corrosion resistant to least corrosion resistant is: Austenitic Cast Iron; 12% Cr = 36% Ni = 9Cr-1Mo; Carbon Steel = Low Alloy Steels; and Cast Iron. Since the materials to be employed in the Advanced Conceptual Design (ACD) waste package are considered to be corrosion allowance materials, the austenitic cast irons, high Cr steels, high Ni steels and the high Cr-Mo steels should not be considered as candidates for the outer containment barrier. Based upon the oxidation and corrosion data available for carbon steels, low alloy steels, and cast irons, a suitable list of candidate materials for a corrosion allowance outer barrier for an ACD waste package could include, A516, 2.25%Cr -- 1%Mo Steel, and A27

Control and tracking arrangements for solid low-level waste disposals to the UK Drigg disposal site

International Nuclear Information System (INIS)

Elgie, K.G.; Grimwood, P.D.

1993-01-01

The Drigg disposal site has been the principal disposal site for solid low-level radioactive wastes (LLW) in the United Kingdom since 1959. It is situated on the Cumbrian coast, some six kilometers to the south of the Sellafield nuclear reprocessing site. The Drigg site receives LLW from a wide range of sources including nuclear power generation, nuclear fuel cycle activities, defense activities, isotope manufacture, universities, hospitals, general industry and clean-up of contaminated sites. This LLW has been disposed of in a series of trenches cut into the underlying clay layer of the site, and, since 1988, also into concrete lined vault. The total volume of LLW disposed of at Drigg is at present in the order of 800,000m 3 , with disposals currently approximately 25,000m 3 per year. British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site. To meet operational and regulatory requirements, BNFL needs to ensure the acceptability of the disposed waste and be able to track it from its arising point to its specific disposal location. This paper describes the system that has been developed to meet these requirements

Near-surface land disposal

International Nuclear Information System (INIS)

Kittel, J.H.

1989-01-01

The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

Disposal options for disused radioactive sources

International Nuclear Information System (INIS)

2005-01-01

This report presents a review of relevant information on the various technical factors and issues, as well as approaches and relevant technologies, leading to the identification of potential disposal options for disused radioactive sources. The report attempts to provide a logical 'road map' for the disposal of disused radioactive sources, taking into consideration the high degree of variability in the radiological properties of such types of radioactive waste. The use of borehole or shaft type repositories is highlighted as a potential disposal option, particularly for those countries that have limited resources and are looking for a simple, safe and cost effective solution for the disposal of their radioactive source inventories. It offers information about usage and characteristics of radioactive sources, disposal considerations, identification and screening of disposal options as well as waste packaging and acceptance criteria for disposal. The information provided in the report could be adapted or adopted to identify and develop specific disposal options suitable for the type and inventory of radioactive sources kept in storage in a given Member State

Disposal of tritium-exposed metal hydrides

International Nuclear Information System (INIS)

Nobile, A.; Motyka, T.

1991-01-01

A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R ampersand D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed

Disposal of Iodine-129

International Nuclear Information System (INIS)

Morgan, M.T.; Moore, J.G.; Devaney, H.E.; Rogers, G.C.; Williams, C.; Newman, E.

1978-01-01

One of the problems to be solved in the nuclear waste management field is the disposal of radioactive iodine-129, which is one of the more volatile and long-lived fission products. Studies have shown that fission products can be fixed in concrete for permanent disposal. Current studies have demonstrated that practical cementitious grouts may contain up to 18% iodine as barium iodate. The waste disposal criterion is based on the fact that harmful effects to present or future generations can be avoided by isolation and/or dilution. Long-term isolation is effective in deep, dry repositories; however, since penetration by water is possible, although unlikely, release was calculated based on leach rates into water. Further considerations have indicated that sea disposal on or in the ocean floor may be a more acceptable alternative

Sub-seabed disposal of radioactive wastes

International Nuclear Information System (INIS)

Sivintsaev, Yu.V.

1990-01-01

The first stage of investigations of possibility of sub-seabed disposal of long-living intermediate-level radioactive wastes carried out by NIREX (UK) is described. Advantages and disadvantages of sub-seabed disposal of radioactive wastes are considered; regions suitable for disposal, transport means for marine disposal are described. Three types of sub-seabed burials are characterized

Financing of radioactive waste disposal

International Nuclear Information System (INIS)

Reich, J.

1989-01-01

Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP) [de

A preliminary analysis of the risk of transporting nuclear waste to potential candidate commercial repository sites

International Nuclear Information System (INIS)

Madsen, M.M.

1984-01-01

In accordance with the provisions of the Nuclear Waste Policy Act of 1982, environmental assessments for potential candidate sites are required to provide a basis for selection of the first site for disposal of commercial radioactive waste in deep geologic repositories. A preliminary analysis of the impacts of transportation for each of the five potential sites will be described. Transportation was assumed to be entirely by truck or entirely by rail in order to obtain bounding impacts. This paper presents both radiological and nonradiological risks for the once-through fuel cycle

Social dimensions of nuclear waste disposal

Energy Technology Data Exchange (ETDEWEB)

Grunwald, Armin [Karlsruhe Institute of Technology, Karlsruhe (Germany). Inst. for Technology Assessment and Systems Analysis

2015-07-01

Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

Phytoextraction crop disposal--an unsolved problem

International Nuclear Information System (INIS)

Sas-Nowosielska, A.; Kucharski, R.; Malkowski, E.; Pogrzeba, M.; Kuperberg, J.M.; Krynski, K.

2004-01-01

Several methods of contaminated crop disposal after phytoextraction process (composting, compaction, incineration, ashing, pyrolysis, direct disposal, liquid extraction) have been described. Advantages and disadvantages of methods are presented and discussed. Composting, compaction and pyrolysis are the pretreatment steps, since significant amount of contaminated biomass will still exist after each of the process. Four methods of final disposal were distinguished: incineration, direct disposal, ashing and liquid extraction. Among them, incineration (smelting) is proposed as the most feasible, economically acceptable and environmentally sound. - Methods of contaminated crop disposal are described and evaluated

Social dimensions of nuclear waste disposal

International Nuclear Information System (INIS)

Grunwald, Armin

2015-01-01

Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

Land disposal alternatives for low-level waste

International Nuclear Information System (INIS)

Alexander, P.; Lindeman, R.; Saulnier, G.; Adam, J.; Sutherland, A.; Gruhlke, J.; Hung, C.

1982-01-01

The objective of this project is to develop data regarding the effectiveness and costs of the following options for disposing of specific low-level nuclear waste streams; sanitary landfill; improved shallow land burial; intermediate depth disposal; deep well injection; conventional shallow land burial; engineered surface storage; deep geological disposal; and hydrofracturing. This will be accomplished through the following steps: (1) characterize the properties of the commercial low-level wastes requiring disposal; (2) evaluate the various options for disposing of this waste, characterize selected representative waste disposal sites and design storage facilities suitable for use at those sites; (3) calculate the effects of various waste disposal options on population health risks; (4) estimate the costs of various waste disposal options for specific sites; and (5) perform trade-off analyses of the benefits of various waste disposal options against the costs of implementing these options. These steps are described. 2 figures, 2 tables

Unreviewed Disposal Question: A Discipline Process to Manage Change in LLW Disposal

International Nuclear Information System (INIS)

Goldston, W.T.

2000-01-01

The Department of Energy's waste management Order, DOE O 435.1, requires that low--level waste disposal facilities develop and maintain a radiological performance assessment to ensure that disposal operations are within a performance envelope defined by performance objectives for long-term protection of the public and the environment. The Order also requires that a radiological composite analysis be developed and maintained to ensure that the disposal facility, in combination with other sources of radioactive material that may remain when all DOE activities have ceased, will not compromise future radiological protection of the public and the environment. The Order further requires that a Disposal Authorization Statement (DAS) be obtained from DOE Headquarters and that the disposal facility be operated within the performance assessment, composite analysis, and DAS. Maintenance of the performance assessment and composite analysis includes conducting test, research, and monitoring activities to increase confidence in the results of the analyses. It also includes updating the analyses as changes are proposed in the disposal operations, or other information requiring an update, becomes available. Personnel at the Savannah River Site have developed and implemented an innovative process for reviewing proposed or discovered changes in low-level radioactive waste disposal operations. The process is a graded approach to determine, in a disciplined manner, whether changes are within the existing performance envelope, as defined by the performance assessment, composite analysis, and DAS, or whether additional analysis is required to authorize the change. This process is called the Unreviewed Disposal Question (UDQ) process. It has been developed to be analogous to the Unreviewed Safety Question (UDQ) process that has been in use within DOE for many years. This is the first formalized system implemented in the DOE complex to examine low-level waste disposal changes the way the

Subseabed disposal safety analysis

International Nuclear Information System (INIS)

Koplick, C.M.; Kabele, T.J.

1982-01-01

This report summarizes the status of work performed by Analytic Sciences Corporation (TASC) in FY'81 on subseabed disposal safety analysis. Safety analysis for subseabed disposal is divided into two phases: pre-emplacement which includes all transportation, handling, and emplacement activities; and long-term (post-emplacement), which is concerned with the potential hazard after waste is safely emplaced. Details of TASC work in these two areas are provided in two technical reports. The work to date, while preliminary, supports the technical and environmental feasibility of subseabed disposal of HLW

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Dlouhy, Z.

1982-01-01

This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

The project for national disposal facility for low and intermediate level radioactive waste in Bulgaria

International Nuclear Information System (INIS)

Alexandrov, A.; Boyanov, S.; Christoskova, M.; Ivanov, A.

2006-01-01

The State Enterprise Radioactive Waste is the responsible organisation in Bulgaria for the radioactive waste management and, in particular, for the establishment of the national disposal facility (NDF) for low and intermediate level short-lived radioactive waste (LIL RAW SL). According to the national strategy for the safe management of spent fuel and radioactive waste the NDF should be commissioned in 2015. NDF will accept two main waste streams - for disposal and for storage if the waste is not disposable. The major part of disposable waste is generated by Kozloduy NPP. The disposal facility will be a near surface module type engineered facility. Consecutive erection of new modules will be available in order to increase the capacity of the facility. The corrective measures are previewed to be applied if needed - upgrading of engineered barriers and/or retrieval of the waste. The active control after the facility is closed should be not more than 300 years. The safety of the facility is supposed to be based on the passive measures based on defense in deep consisting of physical barriers and administrative measures. A multi barrier approach will be applied. Presently the NDF project is at the first stage of the facility life cycle - the site selection. The siting process itself consists of four stages - elaboration of a concept for waste disposal and site selection planning, data collection and region analyses, characterization of the preferred sites-candidates and site confirmation. Up till now the work on the first two stages of the siting process had been done by the SE RAW. Geological site investigations have been carried out for more than two decades all over the territory of the country. The results of the investigations have been summarized and analysed thoroughly. More than 40 potential sites have been considered, after the preselection 12 sites have been selected as favourable and among them 5 are pointed out as acceptable. The ultimate decision for a site

Overview of nuclear waste disposal in space

International Nuclear Information System (INIS)

Rice, E.E.; Priest, C.C.

1981-01-01

One option receiving consideration by the Department of Energy (DOE) is the space disposal of certain high-level nuclear wastes. The National Aeronautics and Space Administration is assessing the space disposal option in support of DOE studies on alternatives for nuclear waste management. The space disposal option is viewed as a complement, since total disposal of fuel rods from commercial power plants is not considered to be economically practical with Space Shuttle technology. The space disposal of certain high-level wastes may, however, provide reduced calculated and perceived risks. The space disposal option in conjunction with terrestrial disposal may offer a more flexible and lower risk overall waste management system. For the space disposal option to be viable, it must be demonstrated that the overall long-term risks associated with this activity, as a complement to the mined geologic repository, would be significantly less than the long-term risk associated with disposing of all the high-level waste. The long-term risk benefit must be achieved within an acceptable short-term and overall program cost. This paper briefly describes space disposal alternatives, the space disposal destination, possible waste mixes and forms, systems and typical operations, and the energy and cost analysis

HLW disposal dilemma

International Nuclear Information System (INIS)

Andrei, V.; Glodeanu, F.

2003-01-01

The radioactive waste is an inevitable residue from the use of radioactive materials in industry, research and medicine, and from the operation of generating electricity nuclear power stations. The management and disposal of such waste is therefore an issue relevant to almost all countries. Undoubtedly the biggest issue concerning radioactive waste management is that of high level waste. The long-lived nature of some types of radioactive wastes and the associated safety implications of disposal plans have raised concern amongst those who may be affected by such facilities. For these reasons the subject of radioactive waste management has taken on a high profile in many countries. Not one Member State in the European Union can say that their high level waste will be disposed of at a specific site. Nobody can say 'that is where it is going to go'. Now, there is a very broad consensus on the concept of geological disposal. The experts have little, if any doubt that we could safely dispose of the high level wastes. Large sectors of the public continue to oppose to most proposals concerning the siting of repositories. Given this, it is increasingly difficult to get political support, or even political decisions, on such sites. The failure to advance to the next step in the waste management process reinforces the public's initial suspicion and resistance. In turn, this makes the political decisions even harder. In turn, this makes the political decisions even harder. The management of spent fuel from nuclear power plant became a crucial issue, as the cooling pond of the Romanian NPP is reaching saturation. During the autumn of 2000, the plant owner proceeded with an international tendering process for the supply of a dry storage system to be implemented at the Cernavoda station to store the spent fuel from Unit 1 and eventually from Unit 2 for a minimum period of 50 years. The facility is now in operation. As concern the disposal of the spent fuel, the 'wait and see

Engineering geology of waste disposal

International Nuclear Information System (INIS)

Bentley, S.P.

1996-01-01

This volume covers a wide spectrum of activities in the field of waste disposal. These activities range from design of new landfills and containment properties of natural clays to investigation, hazard assessment and remediation of existing landfills. Consideration is given to design criteria for hard rock quarries when used for waste disposal. In addition, an entire section concerns the geotechnics of underground repositories. This covers such topics as deep drilling, in situ stress measurement, rock mass characterization, groundwater flows and barrier design. Engineering Geology of Waste Disposal examines, in detail, the active role of engineering geologists in the design of waste disposal facilities on UK and international projects. The book provides an authoritative mix of overviews and detailed case histories. The extensive spectrum of papers will be of practical value to those geologists, engineers and environmental scientists who are directly involved with waste disposal. (UK)

Waste Water Disposal Design And Management I

International Nuclear Information System (INIS)

Yang, Sang Hyeon; Lee, Jung Su

2004-04-01

This book gives descriptions of waste water disposal, design and management, which includes design of waterworks and sewerage facility such as preparatory work and building plan, used waste water disposal facilities, waste water disposal plant and industrial waste water disposal facilities, water use of waste water disposal plant and design of pump and pump facilities such as type and characteristic, selection and plan, screening and grit.

Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

Energy Technology Data Exchange (ETDEWEB)

Veil, J.A.

1997-09-01

According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

A study on nuclide migration in buffer materials and rocks for geological disposal of radioactive waste

International Nuclear Information System (INIS)

Sato, Haruo

1998-01-01

This thesis summarizes the results investigated in order to establish a basic theory on the predictive method of diffusion coefficients of nuclides in compacted sodium bentonite which is a candidate buffer material and in representative rocks for the geological disposal of radioactive waste by measuring the pore structural factors of the compacted bentonite and rocks such as porosity and tortuosity, measuring diffusion coefficients of nuclides in the bentonite and rocks, acquiring basic data on diffusion and developing diffusion models which can quantitatively predict nuclide migration in long-term. (J.P.N.). 117 refs

A practical approach to the disposal of highly toxic and long-lived spent nuclear fuel waste between Venus and Earth

International Nuclear Information System (INIS)

Ehricke, K.A.

1983-01-01

Extraterrestrial disposal, while not the only alternative, nevertheless assures definite and irreversible removal of the most toxic and long-lived waste from the biosphere. The disposal 'site' should lie at minimum safe transfer energy level. Primary candidate is the space between Venus and Earth. The number of propulsion phases should be a minimum, preferably only one. Lunar gravity assist can be helpful to achieve higher inclination of the heliocentric orbit relative to the ecliptic. Solidified spent fuel isotopes and actinides, sufficient to reduce the residual terrestrial waste to the radiation level of natural uranium deposits after 30 to 40 yr instead of 1000 to 1500 yr, is deposited into heliocentric orbits. Transportation systems, requirements, costs and the associated socio-economic benefit potentials of an environmentally more benign and a more vigorous nuclear power generation program are presented. Prior to solidification, an interim storage of 10 yr, following removal from the reactor, may be required. The Shuttle, with one Orbiter modified as Nuclear Waste Carrying Orbiter and an out of near-Earth orbit booster, provides a safe and economic transportation system at disposal mission costs from surface to disposal orbit of less than 0.5 cents/kWhe or <= 0.1 cent/kWhe depending on level of orbital operations. Details are discussed. (author)

Efficiency analyses of the CANDU spent fuel repository using modified disposal canisters for a deep geological disposal system design

International Nuclear Information System (INIS)

Lee, J.Y.; Cho, D.K.; Lee, M.S.; Kook, D.H.; Choi, H.J.; Choi, J.W.; Wang, L.M.

2012-01-01

Highlights: ► A reference disposal concept for spent nuclear fuels in Korea has been reviewed. ► To enhance the disposal efficiency, alternative disposal concepts were developed. ► Thermal analyses for alternative disposal concepts were performed. ► From the result of the analyses, the disposal efficiency of the concepts was reviewed. ► The most effective concept was suggested. - Abstract: Deep geological disposal concept is considered to be the most preferable for isolating high-level radioactive waste (HLW), including nuclear spent fuels, from the biosphere in a safe manner. The purpose of deep geological disposal of HLW is to isolate radioactive waste and to inhibit its release of for a long time, so that its toxicity does not affect the human beings and the biosphere. One of the most important requirements of HLW repository design for a deep geological disposal system is to keep the buffer temperature below 100 °C in order to maintain the integrity of the engineered barrier system. In this study, a reference disposal concept for spent nuclear fuels in Korea has been reviewed, and based on this concept, efficient alternative concepts that consider modified CANDU spent fuels disposal canister, were developed. To meet the thermal requirement of the disposal system, the spacing of the disposal tunnels and that of the disposal pits for each alternative concept, were drawn following heat transfer analyses. From the result of the thermal analyses, the disposal efficiency of the alternative concepts was reviewed and the most effective concept suggested. The results of these analyses can be used for a deep geological repository design and detailed analyses, based on exact site characteristics data, will reduce the uncertainty of the results.

Program for responsible and safe disposal of spent fuel elements and radioactive wastes (National disposal program)

International Nuclear Information System (INIS)

2015-01-01

The contribution covers the following topics: fundamentals of the disposal policy; amount of radioactive wastes and prognosis; disposal of radioactive wastes - spent fuel elements and wastes from waste processing, radioactive wastes with low heat production; legal framework of the nuclear waste disposal in Germany; public participation, cost and financing.

Update on the Federal Facilities Compliance Act disposal workgroup disposal site evaluation - what has worked and what has not

International Nuclear Information System (INIS)

Case, J.T.; Waters, R.D.

1995-01-01

The Department of Energy (DOE) has been developing a planning process for mixed low-level waste (MLLW) disposal in conjunction with the affected states for over two years and has screened the potential disposal sites from 49 to 15. A radiological performance evaluation was conducted on these fifteen sites to further identify their strengths and weaknesses for disposal of MLLW. Technical analyses are on-going. The disposal evaluation process has sufficiently satisfied the affected states' concerns to the point that disposal has not been a major issue in the consent order process for site treatment plans. Additionally, a large amount of technical and institutional information on several DOE sites has been summarized. The relative technical capabilities of the remaining fifteen sites have been demonstrated, and the benefits of waste form and disposal facility performance have been quantified. However, the final disposal configuration has not yet been determined. Additionally, the MLLW disposal planning efforts will need to integrate more closely with the low-level waste disposal activities before a final MLLW disposal configuration can be determined. Recent Environmental Protection Agency efforts related to the definition of hazardous wastes may also affect the process

Generalized economic model for evaluating disposal costs at a low-level waste disposal facility

International Nuclear Information System (INIS)

Baird, R.D.; Rogers, V.C.

1985-01-01

An economic model is developed which can be used to evaluate cash flows associated with the development, operations, closure, and long-term maintenance of a proposed Low-Level Radioactive Waste disposal facility and to determine the unit disposal charges and unit surcharges which might result. The model includes the effects of nominal interest rate (rate of return on investment, or cost of capital), inflation rate, waste volume growth rate, site capacity, duration of various phases of the facility history, and the cash flows associated with each phase. The model uses standard discounted cash flow techniques on an after-tax basis to determine that unit disposal charge which is necessary to cover all costs and expenses and to generate an adequate rate of return on investment. It separately considers cash flows associated with post-operational activities to determine the required unit surcharge. The model is applied to three reference facilities to determine the respective unit disposal charges and unit surcharges, with various values of parameters. The sensitivity of the model results are evaluated for the unit disposal charge

radioactive waste disposal standards abroad

International Nuclear Information System (INIS)

Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

2012-01-01

With the world focus on human health and environmental protection, the problem of radioactive waste disposal has gradually become a global issue, and the focus of attention of public. The safety of radioactive waste disposal, is not only related to human health and environmental safety, but also an important factor of affecting the sustainable development of nuclear energy. In recent years the formulation of the radioactive waste disposal standards has been generally paid attention to at home and abroad, and it has made great progress. In China, radioactive waste management standards are being improved, and there are many new standards need to be developed. The revised task of implement standards is very arduous, and there are many areas for improvement about methods and procedures of the preparation of standards. This paper studies the current situation of radioactive waste disposal standards of the International Atomic Energy Agency, USA, France, Britain, Russia, Japan, and give some corresponding recommendations of our radioactive waste disposal standards. (authors)

Disposal of radioactive waste material

International Nuclear Information System (INIS)

Cairns, W.J.; Burton, W.R.

1984-01-01

A method of disposal of radioactive waste consists in disposing the waste in trenches dredged in the sea bed beneath shallow coastal waters. Advantageously selection of the sites for the trenches is governed by the ability of the trenches naturally to fill with silt after disposal. Furthermore, this natural filling can be supplemented by physical filling of the trenches with a blend of absorber for radionuclides and natural boulders. (author)

48 CFR 2845.603 - Disposal methods.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Disposal methods. 2845.603 Section 2845.603 Federal Acquisition Regulations System DEPARTMENT OF JUSTICE Contract Management GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 2845.603 Disposal methods...

48 CFR 945.603 - Disposal methods.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Disposal methods. 945.603 Section 945.603 Federal Acquisition Regulations System DEPARTMENT OF ENERGY CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 945.603 Disposal methods. ...

Safety of direct disposal of spent fuel and of disposal of reprocessing waste

Energy Technology Data Exchange (ETDEWEB)

Besnus, F. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Fontenay-aux-Roses (France)

2006-07-01

In 2005, the French Agency for Radioactive waste management (ANDRA) established a report on the feasibility of the geological disposal of high level and intermediate level long lived radioactive waste, in a clay formation. The hypothesis of spent fuel direct disposal was also considered. By the end of 2005, IRSN performed a complete technical review of ANDRA's report, aiming at highlighting the salient safety issues that were to be addressed within a process that may possibly lead to the creation of a disposal facility for these wastes. The following publication presents the main conclusions of this technical review. (author)

Safety of direct disposal of spent fuel and of disposal of reprocessing waste

International Nuclear Information System (INIS)

Besnus, F.

2006-01-01

In 2005, the French Agency for Radioactive waste management (ANDRA) established a report on the feasibility of the geological disposal of high level and intermediate level long lived radioactive waste, in a clay formation. The hypothesis of spent fuel direct disposal was also considered. By the end of 2005, IRSN performed a complete technical review of ANDRA's report, aiming at highlighting the salient safety issues that were to be addressed within a process that may possibly lead to the creation of a disposal facility for these wastes. The following publication presents the main conclusions of this technical review. (author)

Geological disposal system development

Energy Technology Data Exchange (ETDEWEB)

Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

2000-04-01

Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected.

Geological disposal system development

International Nuclear Information System (INIS)

Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

2000-04-01

Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected

Prediction of long-term behaviour for nuclear waste disposal

International Nuclear Information System (INIS)

Shoesmith, D.W.; Ikeda, B.M.; King, F.; Sunder, S.

1996-09-01

The modelling procedures developed for the long-term prediction of the corrosion of used fuel and of titanium and copper nuclear waste containers are described. The corrosion behaviour of these materials changes with time as the conditions within the conceptual disposal vault evolve from an early warm, oxidizing phase to an indefinite period of cool, anoxic conditions. For the two candidate container materials, this evolution of conditions means that the containers will be initially susceptible to localized corrosion but that in the long-term, corrosion should be more general in nature. The propagation of the pitting of Cu and of the crevice corrosion of Ti alloys is modelled using statistical models. General corrosion processes are modelled deterministically. For the fuel, deterministic electrochemical models have been developed to predict the long-term dissolution rate of U0 2 . The corrosion behaviour of materials in the disposal vault can be influenced by reengineering the vault environment. For instance, increasing the areal loading of containers will produce higher vault temperatures resulting in more extensive drying of the porous backfill materials. The initiation of crevice corrosion on Ti may then be delayed, leading to longer container lifetimes. For copper containers, minimizing the amount Of O 2 initially trapped in the pores of the backfill, or adding reducing agents to consume this O 2 faster, will limit the extent of corrosion, permitting a reduction of the container wall thickness necessary for containment. (author). 55 refs., 19 figs

Waste disposal

CERN Multimedia

2006-01-01

We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container. type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3). nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.). building concerned. details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting o...

Waste disposal

CERN Multimedia

2006-01-01

We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container; type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3); nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.); building concerned; details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting...

No nuclear power. No disposal facility?

Energy Technology Data Exchange (ETDEWEB)

Feinhals, J. [DMT GmbH und Co.KG, Hamburg (Germany)

2016-07-01

Countries with a nuclear power programme are making strong efforts to guarantee the safe disposal of radioactive waste. The solutions in those countries are large disposal facilities near surface or in deep geological layers depending on the activity and half-life of the nuclides in the waste. But what will happen with the radioactive waste in countries that do not have NPPs but have only low amounts of radioactive waste from medical, industrial and research facilities as well as from research reactors? Countries producing only low amounts of radioactive waste need convincing solutions for the safe and affordable disposal of their radioactive waste. As they do not have a fund by an operator of nuclear power plants, those countries need an appropriate and commensurate solution for the disposal of their waste. In a first overview five solutions seem to be appropriate: (i) the development of multinational disposal facilities by using the existing international knowhow; (ii) common disposal with hazardous waste; (iii) permanent storage; (iv) use of an existing mine or tunnel; (v) extension of the borehole disposal concept for all the categories of radioactive wastes.

Geological aspects of radioactive waste disposal

International Nuclear Information System (INIS)

Kobera, P.

1985-01-01

Geological formations suitable for burying various types of radioactive wastes are characterized applying criteria for the evaluation and selection of geological formations for building disposal sites for radioactive wastes issued in IAEA technical recommendations. They are surface disposal sites, disposal sites in medium depths and deep disposal sites. Attention is focused on geological formations usable for injecting self-hardening mixtures into cracks prepared by hydraulic decomposition and for injecting liquid radioactive wastes into permeable rocks. Briefly outlined are current trends of the disposal of radioactive wastes in Czechoslovakia and the possibilities are assessed from the geological point of view of building disposal sites for radioactive wastes on the sites of Czechoslovak nuclear power plants at Jaslovske Bohunice, Mochovce, Dukovany, Temelin, Holice (eastern Bohemia), Blahoutovice (northern Moravia) and Zehna (eastern Slovakia). It is stated that in order to design an optimal method of the burial of radioactive waste it will be necessary to improve knowledge of geological conditions in the potential disposal sites at the said nuclear plants. There is usually no detailed knowledge of geological and hydrological conditions at greater depths than 100 m. (Z.M.)

Comparison of the waste management aspects of spent fuel disposal and reprocessing: post-disposal radiological impact

International Nuclear Information System (INIS)

Mobbs, S.F.; Harvey, M.P.; Martin, J.S.; Mayall, A.; Jones, M.E.

1991-01-01

A joint project involving contractors from France, Germany and the UK was set up by the Commission of the European Communities to assess the implications of two waste management options: the direct disposal of spent fuel and reprocessing of that fuel. This report describes the calculation of the radiological impact on the public of the management and disposal of the wastes associated with these two options. Six waste streams were considered: discharge of liquid reprocessing effluents, discharge of gaseous reprocessing effluents, disposal of low-level solid wastes arising from reprocessing, disposal of intermediate-level solid wastes arising from reprocessing, disposal of vitrified high-level reprocessing wastes, and direct disposal of spent fuel. The results of the calculations are in the form of maximum annual doses and risks to individual members of the public, and collective doses to four population groups, integrated over six time periods. These results were designed for input into a computer model developed by another contractor, Yard Ltd, which combines costs and impacts in a multi-attribute hierarchy to give an overall measure of the impact of a given option

36 CFR 228.57 - Types of disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Types of disposal. 228.57... Disposal of Mineral Materials Types and Methods of Disposal § 228.57 Types of disposal. Except as provided... qualified bidder after formal advertising and other appropriate public notice; (b) Sale by negotiated...

7 CFR 2902.21 - Disposable containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposable containers. 2902.21 Section 2902.21... Items § 2902.21 Disposable containers. (a) Definition. Products designed to be used for temporary... paragraph (d): Disposable containers can include boxes and packaging made from paper. Under the Resource...

Solid waste disposal into salt mines

International Nuclear Information System (INIS)

Repke, W.

1981-01-01

The subject is discussed as follows: general introduction to disposal of radioactive waste; handling of solid nuclear waste; technology of final disposal, with specific reference to salt domes; conditioning of radioactive waste; safety barriers for radioactive waste; practice of final disposal in other countries. (U.K.)

Shallow ground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This guidebook outlines the factors to be considered in site selection, design, operation, shut-down and surveillance as well as the regulatory requirements of repositories for safe disposal of radioactive waste in shallow ground. No attempt is made to summarize the existing voluminous literature on the many facets of radioactive waste disposal. In the context of this guidebook, shallow ground disposal refers to the emplacement of radioactive waste, with or without engineered barriers, above or below the ground surface, where the final protective covering is of the order of a few metres thick. Deep geological disposal and other underground disposal methods, management of mill tailings and disposal into the sea have been or will be considered in other IAEA publications. These guidelines have been made sufficiently general to cover a broad variety of climatic, hydrogeological and biological conditions. They may need to be interpreted or modified to reflect local conditions and national regulations

Classification and disposal of radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.

1990-01-01

This paper reviews the historical development in the U.S. of definitions and requirements for permanent disposal of different classes of radioactive waste. We first consider the descriptions of different waste classes that were developed prior to definitions in laws and regulations. These descriptions usually were not based on requirements for permanent disposal but, rather, on the source of the waste and requirements for safe handling and storage. We then discuss existing laws and regulations for disposal of different waste classes. Current definitions of waste classes are largely qualitative, and thus somewhat ambiguous, and are based primarily on the source of the waste rather than the properties of its radioactive constituents. Furthermore, even though permanent disposal is clearly recognized as the ultimate goal of radioactive water management, current laws and regulations do not associated the definitions of different waste classes with requirement for particular disposal systems. Thus, requirements for waste disposal essentially are unaffected by ambiguities in the present waste classification system

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Blomeke, J.O.

1979-01-01

Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

Solving multi-objective facility location problem using the fuzzy analytical hierarchy process and goal programming: a case study on infectious waste disposal centers

Directory of Open Access Journals (Sweden)

Narong Wichapa

Full Text Available The selection of a suitable location for infectious waste disposal is one of the major problems in waste management. Determining the location of infectious waste disposal centers is a difficult and complex process because it requires combining social and environmental factors that are hard to interpret, and cost factors that require the allocation of resources. Additionally, it depends on several regulations. Based on the actual conditions of a case study, forty hospitals and three candidate municipalities in the sub-Northeast region of Thailand, we considered multiple factors such as infrastructure, geological and social & environmental factors, calculating global priority weights using the fuzzy analytical hierarchy process (FAHP. After that, a new multi-objective facility location problem model which combines FAHP and goal programming (GP, namely the FAHP-GP model, was tested. The proposed model can lead to selecting new suitable locations for infectious waste disposal by considering both total cost and final priority weight objectives. The novelty of the proposed model is the simultaneous combination of relevant factors that are difficult to interpret and cost factors, which require the allocation of resources. Keywords: Multi-objective facility location problem, Fuzzy analytic hierarchy process, Infectious waste disposal centers

Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: A case study in southern China

International Nuclear Information System (INIS)

Yi, Shuping; Ma, Haiyi; Zheng, Chunmiao; Zhu, Xiaobin; Wang, Hua'an; Li, Xueshan; Hu, Xueling; Qin, Jianbo

2012-01-01

Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world, particularly since a regional strategy for LILW disposal has been implemented to protect humans and the environment. This paper presents a demonstration of the site assessment process through a case study focusing mainly on the geologic, hydrogeologic and geochemical characteristics of the candidate site. A joint on-site and laboratory investigation, supplemented by numerical modeling, was implemented in this assessment. Results indicate that no fault is present in the site area, although there are some minor joints and fractures, primarily showing a north–south trend. Most of the joints are filled with quartz deposits and would thus function hydraulically as impervious barriers. Investigation of local hydrologic boundaries has shown that the candidate site represents an essentially isolated hydrogeologic unit, and that little or no groundwater flow occurs across its boundaries on the north or east, or across the hilly areas to the south. Groundwater in the site area is recharged by precipitation and discharges primarily by evapo-transpiration and surface flow through a narrow outlet to the west. Groundwater flows slowly from the hilly area to the foot of the hills and discharges mainly into the inner brooks and marshes. Some groundwater circulates in deeper granite in a slower manner. The vadose zone in the site was investigated specially for their significant capability for restraining the transport of radionuclides. Results indicate that the vadose zone is up to 38 m in thickness and is made up of alluvial clay soils and very highly weathered granite. The vadose

Radioactive waste disposal in W.A

International Nuclear Information System (INIS)

Hartley, B.M.

1983-01-01

Radioactive waste in Western Australia arises primarily from medical diagnosis and treatment and from scientific research mainly with a medical orientation. Waste is classified before disposal depending on its level and type of radioactivity and then disposed of either to municipal land fill sites, to the sewerage system or by incineration. The amounts of radioactive materials which may be disposed of to the sewers and air are set by the Radiation Safety Act (1975) Regulations, and the land fill operations are controlled to ensure isolation of the material. Other waste such as unwanted sources used in industrial applications are stored for future disposal. Discussions are being held between officers of the State and Australian Governments aimed at providing suitable disposal methods for sources of this kind

36 CFR 13.1118 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1118... Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may...

36 CFR 13.1008 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1008... § 13.1008 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be...

36 CFR 13.1912 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1912....1912 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located...

36 CFR 13.1604 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1604... Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located within one...

Analysis of scenarios for the direct disposal of spent nuclear fuel disposal conditions as expected in Germany

International Nuclear Information System (INIS)

Ashton, P.; Mehling, O.; Mohn, R.; Wingender, H.J.

1990-01-01

This report contains an investigation of aspects of the waste management of spent light water reactor fuel by direct disposal in a deep geological formation on land. The areas covered are: interim dry storage of spent fuel with three options of pre-conditioning; conditioning of spent fuel for final disposal in a salt dome repository; disposal of spent fuel (heat-generating waste) in a salt dome repository; disposal of medium and low-level radioactive wastes in the Konrad mine. Dose commitments, effluent discharges and potential incidents were not found to vary significantly for the various conditioning options/salt dome repository types. Due to uncertainty in the cost estimates, in particular the disposal cost estimates, the variation between the three conditioning options examined is not considered as being significant. The specific total costs for the direct disposal strategy are estimated to lie in the range ECU 600 to 700 per kg hm (basis 1988)

Retrievable disposal - opposing views on ethics

International Nuclear Information System (INIS)

Selling, H.A.

2000-01-01

In the previous decades many research programmes on the disposal of radioactive waste have been completed in the Netherlands. The experts involved have reconfirmed their view that deep underground disposal in suitable geological formations would ensure a safe and prolonged isolation of the waste from the biosphere. Both rock salt and clay formations are considered to qualify as a suitable host rock. In 1993 the government in a position paper stated that such a repository should be designed in a way that the waste can be retrieved from it, should the need arise. In an attempt to involve stakeholders in the decision-making process, a research contract was awarded to an environmental group to study the ethical aspects related to retrievable disposal of radioactive waste. In their report which was published in its final form in January 2000 the authors concluded that retrievable disposal is acceptable from an ethical point of view. However, this conclusion was reached in the understanding that this situation of retrievability would be permanent. From the concept of equity between generations, each successive generation should be offered equal opportunities to decide for itself how to dispose of the radioactive waste. Consequently, the preferred disposal option is retrievable disposal (or long term storage) in a surface facility. Although this view is not in conformity with the ''official'' position on radioactive waste disposal, there is a benefit of having established a dialogue between interested parties in a broad sense. (author)

41 CFR 102-75.415 - What happens after the disposal agency receives the FAA's recommendation for disposal of the...

Science.gov (United States)

2010-07-01

... disposal agency receives the FAA's recommendation for disposal of the property for a public airport? 102-75... receives the FAA's recommendation for disposal of the property for a public airport? The head of the disposal agency, or his or her designee, may convey property approved by the FAA for use as a public...

The Hazardous Waste/Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

Bailey, L.L.

1991-01-01

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996

High-level nuclear waste disposal

International Nuclear Information System (INIS)

Burkholder, H.C.

1985-01-01

The meeting was timely because many countries had begun their site selection processes and their engineering designs were becoming well-defined. The technology of nuclear waste disposal was maturing, and the institutional issues arising from the implementation of that technology were being confronted. Accordingly, the program was structured to consider both the technical and institutional aspects of the subject. The meeting started with a review of the status of the disposal programs in eight countries and three international nuclear waste management organizations. These invited presentations allowed listeners to understand the similarities and differences among the various national approaches to solving this very international problem. Then seven invited presentations describing nuclear waste disposal from different perspectives were made. These included: legal and judicial, electric utility, state governor, ethical, and technical perspectives. These invited presentations uncovered several issues that may need to be resolved before high-level nuclear wastes can be emplaced in a geologic repository in the United States. Finally, there were sixty-six contributed technical presentations organized in ten sessions around six general topics: site characterization and selection, repository design and in-situ testing, package design and testing, disposal system performance, disposal and storage system cost, and disposal in the overall waste management system context. These contributed presentations provided listeners with the results of recent applied RandD in each of the subject areas

Deep disposal of long-lived radioactive waste in France: The volunteering approach in site selection

International Nuclear Information System (INIS)

Raynal, M.; Barber, P.

1995-01-01

The French Waste Act of December 1991 set up important dispositions among which the deep disposal of long-lived waste should be evaluated before 2006. ANDRA, the French National Agency for Radioactive Waste Management, is particularly responsible for the siting, the construction and the operation of underground laboratories designed to study potential geologic host-formations for deep disposal. An open decision-making process started up in 1992, specially to restore the public confidence after strong contest in the early 1990. The mission of negotiation conducted in 1993 all over the country by the appointed Member of Parliament, Mr. Bataille, allowed volunteer candidates for the siting surveyed by ANDRA in 1994 and 1995. Four areas are presently under characterization investigations, proceeding with the first phase of the underground laboratory program with the objective of choosing two sites for two underground laboratories. France is now entering a new and very important phase on the long path towards the creation of an underground repository where public's understanding and acceptance is an important part of the overall process as it is shown in this paper

Spent nuclear fuel disposal liability insurance

International Nuclear Information System (INIS)

Martin, D.W.

1984-01-01

This thesis examines the social efficiency of nuclear power when the risks of accidental releases of spent fuel radionuclides from a spent fuel disposal facility are considered. The analysis consists of two major parts. First, a theoretical economic model of the use of nuclear power including the risks associated with releases of radionuclides from a disposal facility is developed. Second, the costs of nuclear power, including the risks associated with a radionuclide release, are empirically compared to the costs of fossil fuel-fired generation of electricity. Under the provisions of the Nuclear Waste Policy Act of 1982, the federally owned and operated spent nuclear fuel disposal facility is not required to maintain a reserve fund to cover damages from an accidental radionuclide release. Thus, the risks of a harmful radionuclide release are not included in the spent nuclear fuel disposal fee charged to the electric utilities. Since the electric utilities do not pay the full, social costs of spent fuel disposal, they use nuclear fuel in excess of the social optimum. An insurance mechanism is proposed to internalize the risks associated with spent fueled disposal. Under this proposal, the Federal government is required to insure the disposal facility against any liabilities arising from accidental releases of spent fuel radionuclides

Design of the disposal facility 2012

International Nuclear Information System (INIS)

Saanio, T.; Ikonen, A.; Keto, P.; Kirkkomaeki, T.; Kukkola, T.; Nieminen, J.; Raiko, H.

2013-11-01

The spent nuclear fuel accumulated from the nuclear power plants in Olkiluoto in Eurajoki and in Haestholmen in Loviisa will be disposed of in Olkiluoto. A facility complex will be constructed at Olkiluoto, and it will include two nuclear waste facilities according to Government Degree 736/2008. The nuclear waste facilities are an encapsulation plant, constructed to encapsulate spent nuclear fuel and a disposal facility consisting of an underground repository and other underground rooms and above ground service spaces. The repository is planned to be excavated to a depth of 400 - 450 meters. Access routes to the disposal facility are an inclined access tunnel and vertical shafts. The encapsulated fuel is transferred to the disposal facility in the canister lift. The canisters are transferred from the technical rooms to the disposal area via central tunnel and deposited in the deposition holes which are bored in the floors of the deposition tunnels and are lined beforehand with compacted bentonite blocks. Two parallel central tunnels connect all the deposition tunnels and these central tunnels are inter-connected at regular intervals. The solution improves the fire safety of the underground rooms and allows flexible backfilling and closing of the deposition tunnels in stages during the operational phase of the repository. An underground rock characterization facility, ONKALO, is excavated at the disposal level. ONKALO is designed and constructed so that it can later serve as part of the repository. The goal is that the first part of the disposal facility will be constructed under the building permit phase in the 2010's and operations will start in the 2020's. The fuel from 4 operating reactors as well the fuel from the fifth nuclear power plant under construction, has been taken into account in designing the disposal facility. According to the information from TVO and Fortum, the amount of the spent nuclear fuel is 5,440 tU. The disposal facility is being excavated

Disposal phase experimental program plan

International Nuclear Information System (INIS)

1997-01-01

The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes

Greater-confinement disposal

International Nuclear Information System (INIS)

Trevorrow, L.E.; Schubert, J.P.

1989-01-01

Greater-confinement disposal (GCD) is a general term for low-level waste (LLW) disposal technologies that employ natural and/or engineered barriers and provide a degree of confinement greater than that of shallow-land burial (SLB) but possibly less than that of a geologic repository. Thus GCD is associated with lower risk/hazard ratios than SLB. Although any number of disposal technologies might satisfy the definition of GCD, eight have been selected for consideration in this discussion. These technologies include: (1) earth-covered tumuli, (2) concrete structures, both above and below grade, (3) deep trenches, (4) augered shafts, (5) rock cavities, (6) abandoned mines, (7) high-integrity containers, and (8) hydrofracture. Each of these technologies employ several operations that are mature,however, some are at more advanced stages of development and demonstration than others. Each is defined and further described by information on design, advantages and disadvantages, special equipment requirements, and characteristic operations such as construction, waste emplacement, and closure

Waste disposal options report. Volume 1

International Nuclear Information System (INIS)

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01

This report summarizes the potential options for the processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical Processing Plant. It compares the proposed waste-immobilization processes, quantifies and characterizes the resulting waste forms, identifies potential disposal sites and their primary acceptance criteria, and addresses disposal issues for hazardous waste

Disposal of radioactive wastes. Chapter 11

International Nuclear Information System (INIS)

Skitt, J.

1979-01-01

An account is given of the history and present position of legislation in the United Kingdom on the disposal of radioactive wastes. The sections are headed: introduction and definitions; history; the Radioactive Substances Act 1960; disposal of solid radioactive wastes through Local Authority services; function of Local Authorities; exemptions; national radioactive waste disposal service; incidents involving radioactivity. (U.K.)

Oil statistics 1976: supply and disposal

Energy Technology Data Exchange (ETDEWEB)

1976-01-01

Summary tables are included for the period 1960 to 1976. The detailed tables for 1976 cover production, supply and disposal; supply and disposal by product; imports by sources; imports from member countries; exports by destination; exports to member countries; consumption by end-use sectors; and supply and disposal of finished products by country (1975 and 1976). (DLC)

Recycling And Disposal Of Waste

Energy Technology Data Exchange (ETDEWEB)

Choi, Ui So

1987-01-15

This book introduces sewage disposal sludge including properties of sludge and production amount, stabilization of sludge by anaerobic digestion stabilization of sludge by aerobic digestion, stabilization of sludge by chemical method, and dewatering, water process sludge, human waste and waste fluid of septic tank such as disposal of waste fluid and injection into the land, urban waste like definition of urban waste, collection of urban waste, recycling, properties and generation amount, and disposal method and possibility of injection of industrial waste into the ground.

Geohydrology of industrial waste disposal site

International Nuclear Information System (INIS)

Gaynor, R.K.

1984-01-01

An existing desert site for hazardous chemical and low-level radioactive waste disposal is evaluated for suitability. This site is characterized using geologic, geohydrologic, geochemical, and other considerations. Design and operation of the disposal facility is considered. Site characteristics are also evaluated with respect to new and proposed regulatory requirements under the Resource Conservation and Recovery Act (1976) regulations, 40 CFR Part 264, and the ''Licensing Requirements for Landfill Disposal of Radioactive Waste,'' 10 CRF Part 61. The advantages and disadvantages of siting new disposal facilities in similar desert areas are reviewed and contrasted to siting in humid locations

ICRP guidance on radioactive waste disposal

International Nuclear Information System (INIS)

Cooper, J.R.

2002-01-01

The International Commission on Radiological Protection (ICRP) issued recommendations for a system of radiological protection in 1991 as the 1990 Recommendations. Guidance on the application of these recommendations in the general area of waste disposal was issued in 1997 as Publication 77 and guidance specific to disposal of solid long-lived radioactive waste was issued as Publication 81. This paper summarises ICRP guidance in radiological protection requirements for waste disposal concentrating on the ones of relevance to the geological disposal of solid radioactive waste. Suggestions are made for areas where further work is required to apply the ICRP guidance. (author)

User's guide to the 'DISPOSALS' model

International Nuclear Information System (INIS)

Groom, M.S.; James, A.R.; Laundy, R.S.

1984-03-01

This report provides a User's Guide to the 'DISPOSALS' computer model and includes instructions on how to set up and run a specific problem together with details of the scope, theoretical basis, data requirements and capabilities of the model. The function of the 'DISPOSALS' model is to make assignments of nuclear waste material in an optimum manner to a number of disposal sites each subject to a number of constraints such as limits on the volume and activity. The user is able to vary the number of disposal sites, the range and limits of the constraints to be applied to each disposal site and the objective function for optimisation. The model is based on the Linear Programming technique and uses CAP Scientific's LAMPS and MAGIC packages. Currently the model has been implemented on CAP Scientific's VAX 11/750 minicomputer. (author)

Environmental impacts of ocean disposal of CO{sub 2}. Final report volume 2, September 1994--August 1996

Energy Technology Data Exchange (ETDEWEB)

Herzog, H.J.; Adams, E.E. [eds.

1996-12-01

One option to reduce atmospheric CO{sub 2} levels is to capture and sequester power plant CO{sub 2}. Commercial CO{sub 2} capture technology, though expensive, exists today. However, the ability to dispose of large quantities of CO{sub 2} is highly uncertain. The deep ocean is one of only a few possible CO{sub 2} disposal options (others are depleted oil and gas wells or deep, confined aquifers) and is a prime candidate because the deep ocean is vast and highly unsaturated in CO{sub 2}. Technically, the term `disposal` is really a misnomer because the atmosphere and ocean eventually equilibrate on a time scale of 1000 years regardless of where the CO{sub 2} is originally discharged. However, peak atmospheric CO{sub 2} concentrations expected to occur in the next few centuries could be significantly reduced by ocean disposal. The magnitude of this reduction will depend upon the quantity of CO{sub 2} injected in the ocean, as well as the depth and location of injection. Ocean disposal of CO{sub 2} will only make sense if the environmental impacts to the ocean are significantly less than the avoided impacts of atmospheric release. In this project, we examined these ocean impacts through a multi-disciplinary effort designed to summarize the current state of knowledge. In the process, we have developed a comprehensive method to assess the impacts of pH changes on passive marine organisms. This final report addresses the following six topics: CO{sub 2} loadings and scenarios, impacts of CO{sub 2} transport, near-field perturbations, far-field perturbations, environmental impacts of CO{sub 2} release, and policy and legal implications of CO{sub 2} release.

Disposal of Radioactive Waste. Specific Safety Requirements

International Nuclear Information System (INIS)

2011-01-01

This publication establishes requirements applicable to all types of radioactive waste disposal facility. It is linked to the fundamental safety principles for each disposal option and establishes a set of strategic requirements that must be in place before facilities are developed. Consideration is also given to the safety of existing facilities developed prior to the establishment of present day standards. The requirements will be complemented by Safety Guides that will provide guidance on good practice for meeting the requirements for different types of waste disposal facility. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Safety requirements for planning for the disposal of radioactive waste; 4. Requirements for the development, operation and closure of a disposal facility; 5. Assurance of safety; 6. Existing disposal facilities; Appendices.

Disposal Site Information Management System

International Nuclear Information System (INIS)

Larson, R.A.; Jouse, C.A.; Esparza, V.

1986-01-01

An information management system for low-level waste shipped for disposal has been developed for the Nuclear Regulatory Commission (NRC). The Disposal Site Information Management System (DSIMS) was developed to provide a user friendly computerized system, accessible through NRC on a nationwide network, for persons needing information to facilitate management decisions. This system has been developed on NOMAD VP/CSS, and the data obtained from the operators of commercial disposal sites are transferred to DSIMS semiannually. Capabilities are provided in DSIMS to allow the user to select and sort data for use in analysis and reporting low-level waste. The system also provides means for describing sources and quantities of low-level waste exceeding the limits of NRC 10 CFR Part 61 Class C. Information contained in DSIMS is intended to aid in future waste projections and economic analysis for new disposal sites

Citizen Candidates Under Uncertainty

OpenAIRE

Eguia, Jon X.

2005-01-01

In this paper we make two contributions to the growing literature on "citizen-candidate" models of representative democracy. First, we add uncertainty about the total vote count. We show that in a society with a large electorate, where the outcome of the election is uncertain and where winning candidates receive a large reward from holding office, there will be a two-candidate equilibrium and no equilibria with a single candidate. Second, we introduce a new concept of equilibrium, which we te...

Nuclear waste disposal in space

Science.gov (United States)

Burns, R. E.; Causey, W. E.; Galloway, W. E.; Nelson, R. W.

1978-01-01

Work on nuclear waste disposal in space conducted by the George C. Marshall Space Flight Center, National Aeronautics and Space Administration, and contractors are reported. From the aggregate studies, it is concluded that space disposal of nuclear waste is technically feasible.

Tritium waste disposal technology in the US

International Nuclear Information System (INIS)

Albenesius, E.L.; Towler, O.A.

1983-01-01

Tritium waste disposal methods in the US range from disposal of low specific activity waste along with other low-level waste in shallow land burial facilities, to disposal of kilocurie amounts in specially designed triple containers in 65' deep augered holes located in an aird region of the US. Total estimated curies disposed of are 500,000 in commercial burial sites and 10 million curies in defense related sites. At three disposal sites in humid areas, tritium has migrated into the ground water, and at one arid site tritium vapor has been detected emerging from the soil above the disposal area. Leaching tests on tritium containing waste show that tritium in the form of HTO leaches readily from most waste forms, but that leaching rates of tritiated water into polymer impregnated concrete are reduced by as much as a factor of ten. Tests on improved tritium containment are ongoing. Disposal costs for tritium waste are 7 to 10 dollars per cubic foot for shallow land burial of low specific activity tritium waste, and 10 to 20 dollars per cubic foot for disposal of high specific activity waste. The cost of packaging the high specific activity waste is 150 to 300 dollars per cubic foot. 18 references

Radioactive waste (disposal)

International Nuclear Information System (INIS)

Jenkin, P.

1985-01-01

The disposal of low- and intermediate-level radioactive wastes was discussed. The following aspects were covered: public consultation on the principles for assessing disposal facilities; procedures for dealing with the possible sites which the Nuclear Industry Radioactive Waste Executive (NIREX) had originally identified; geological investigations to be carried out by NIREX to search for alternative sites; announcement that proposal for a site at Billingham is not to proceed further; NIREX membership; storage of radioactive wastes; public inquiries; social and environmental aspects; safety aspects; interest groups; public relations; government policies. (U.K.)

Geological disposal of radioactive waste. Safety requirements

International Nuclear Information System (INIS)

2006-01-01

This Safety Requirements publication is concerned with providing protection to people and the environment from the hazards associated with waste management activities related to disposal, i.e. hazards that could arise during the operating period and following closure. It sets out the protection objectives and criteria for geological disposal and establishes the requirements that must be met to ensure the safety of this disposal option, consistent with the established principles of safety for radioactive waste management. It is intended for use by those involved in radioactive waste management and in making decisions in relation to the development, operation and closure of geological disposal facilities, especially those concerned with the related regulatory aspects. This publication contains 1. Introduction; 2. Protection of human health and the environment; 3. The safety requirements for geological disposal; 4. Requirements for the development, operation and closure of geological disposal facilities; Appendix: Assurance of compliance with the safety objective and criteria; Annex I: Geological disposal and the principles of radioactive waste management; Annex II: Principles of radioactive waste management

Alternatives for definse waste-salt disposal

International Nuclear Information System (INIS)

Benjamin, R.W.; McDonell, W.R.

1983-01-01

Alternatives for disposal of decontaminated high-level waste salt at Savannah River were reviewed to estimate costs and potential environmental impact for several processes. In this review, the reference process utilizing intermediate-depth burial of salt-concrete (saltcrete) monoliths was compared with alternatives including land application of the decontaminated salt as fertilizer for SRP pine stands, ocean disposal with and without containment, and terminal storage as saltcake in existing SRP waste tanks. Discounted total costs for the reference process and its modifications were in the same range as those for most of the alternative processes; uncontained ocean disposal with truck transport to Savannah River barges and storage as saltcake in SRP tanks had lower costs, but presented other difficulties. Environmental impacts could generally be maintained within acceptable limits for all processes except retention of saltcake in waste tanks, which could result in chemical contamination of surrounding areas on tank collapse. Land application would require additional salt decontamination to meet radioactive waste disposal standards, and ocean disposal without containment is not permitted in existing US practice. The reference process was judged to be the only salt disposal option studied which would meet all current requirements at an acceptable cost

Geological disposal concept hearings

International Nuclear Information System (INIS)

1996-01-01

The article outlines the progress to date on AECL spent-nuclear fuel geological disposal concept. Hearings for discussion, organised by the federal Environmental Assessment Review Panel, of issues related to this type of disposal method occur in three phases, phase I focuses on broad societal issues related to long term management of nuclear fuel waste; phase II will focus on the technical aspects of this method of disposal; and phase III will consist of community visits in New Brunswick, Quebec, Ontario, Manitoba and Saskatchewan. This article provides the events surrounding the first two weeks of phase I hearings (extracted from UNECAN NEWS). In the first week of hearings, where submissions on general societal issues was the focus, there were 50 presentations including those by Natural Resources Canada, Energy Probe, Ontario Hydro, AECL, Canadian Nuclear Society, Aboriginal groups, environmental activist organizations (Northwatch, Saskatchewan Environmental Society, the Inter-Church Uranium Committee, and the Canadian Coalition for Nuclear responsibility). In the second week of hearings there was 33 presentations in which issues related to siting and implementation of a disposal facility was the focus. Phase II hearings dates are June 10-14, 17-21 and 27-28 in Toronto

Waste management, final waste disposal, fuel cycle

International Nuclear Information System (INIS)

Rengeling, H.W.

1991-01-01

Out of the legal poblems that are currently at issue, individual questions from four areas are dealt with: privatization of ultimate waste disposal; distribution of responsibilities for tasks in the field of waste disposal; harmonization and systematization of regulations; waste disposal - principles for making provisions for waste disposal - proof of having made provisions for waste disposal; financing and fees. A distinction has to be made between that which is legally and in particular constitutionally imperative or, as the case may be, permissible, and issues where there is room for political decision-making. Ultimately, the deliberations on the amendment are completely confined to the sphere of politics. (orig./HSCH) [de

Selection criteria for a radioactive waste disposal site in the Republic of South Africa

International Nuclear Information System (INIS)

Toens, P.D.; Hambleton-Jones, B.B.

1986-01-01

A program commenced in 1978 to select a suitable site for the disposal of nuclear waste in South Africa. This entailed the examination of a variety of socio-economic and earthscience related parameters over large parts of South Africa. The site selection program, for which the Geology Department of the Atomic Energy Corporation of South Africa Ltd (AEC) (previously the Nuclear Development Corporation (NUCOR)) accepted responsibility, commenced with an initial screening phase and led to the identification of potentially suitable areas by mid 1980. A site suitability phase involving regional, and subsequently detailed socio-economic, geological, geohydrological and geophysical studies in the areas identified by the screening phase was completed in December 1982. As a result of very positive indications that the district of Namaqualand was the most suitable candidate area it was possible, after further detailed investigations, to identify and purchase a site judged to be suitable for the disposal of low- and intermediate-level waste by February 1983. The area acquired measures some 10 000ha in extent and is situated 100km southeast of Springbok in the northwestern Cape and 600km north of the Koeberg nuclear power station near Cape Town

Disposable products in the hospital waste stream.

OpenAIRE

Gilden, D. J.; Scissors, K. N.; Reuler, J. B.

1992-01-01

Use of disposable products in hospitals continues to increase despite limited landfill space and dwindling natural resources. We analyzed the use and disposal patterns of disposable hospital products to identify means of reducing noninfectious, nonhazardous hospital waste. In a 385-bed private teaching hospital, the 20 disposable products of which the greatest amounts (by weight) were purchased, were identified, and total hospital waste was tabulated. Samples of trash from three areas were so...

Shallow land disposal of radioactive waste

International Nuclear Information System (INIS)

1987-01-01

The application of basic radiation protection concepts and objectives to the disposal of radioactive wastes requires the development of specific reference levels or criteria for the radiological acceptance of each type of waste in each disposal option. This report suggests a methodology for the establishment of acceptance criteria for the disposal of low-level radioactive waste containing long-lived radionuclides in shallow land burial facilities

Design study on containers for geological disposal of high-level radioactive waste. Phase 2

International Nuclear Information System (INIS)

1986-01-01

This study has considered the feasibility of three designs for containers which would isolate the waste from the environment for a minimum period of 500 to 1000 years. The candidate container designs were taken from the results of a previous study by Ove Arup and Partners (1985) and were developed as the study progressed. Their major features can be summarized as follows: Type A: A thin-walled corrosion-resistant metal shell filled with lead or cement grout. Type B: An unfilled thick-walled carbon steel shell. Type C: an unfilled carbon steel shell plated externally with corrosion-resistant metal. Reference repository conditions in clay, granite and salt, reference disposal operations and metals corrosion data have been taken from various European Community radioactive waste management research and engineering projects. The study concludes that design types A and B are feasible in manufacturing terms but design Type C is not. Furthermore, a titanium-palladium alloy is considered the most suitable metal for Type A container shells and lead is the preferred filler. The analysis shows that design Types A and B both have adequate resistance to pressure and temperature loadings and both would resist accidental impact damage when upright. A reduction in waste heat output at disposal would lower the stress levels in Type A containers but would have virtually no effect on Type B. There is insufficient data to compare the relative costs and benefits of design Types A and B. In conclusion design Types A and B are both considered feasible but Type A would require more development than Type B. In both cases further research is needed to confirm the long-term corrosion performance of the candidate materials. It is recommended that model containers should be produced to demonstrate the proposed methods of manufacture and that they should be tested to validate the analytical techniques used

Defense High Level Waste Disposal Container System Description Document

International Nuclear Information System (INIS)

Pettit, N. E.

2001-01-01

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms [IPWF]) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. US Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as co-disposal. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister inserted in the center and/or one or more DOE SNF canisters displacing a HLW canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by

Chemical Waste Management and Disposal.

Science.gov (United States)

Armour, Margaret-Ann

1988-01-01

Describes simple, efficient techniques for treating hazardous chemicals so that nontoxic and nonhazardous residues are formed. Discusses general rules for management of waste chemicals from school laboratories and general techniques for the disposal of waste or surplus chemicals. Lists specific disposal reactions. (CW)

50 CFR 12.33 - Disposal.

Science.gov (United States)

2010-10-01

... other equipment), except wildlife or plants, in accordance with current Federal Property Management..., TRANSPORTATION, SALE, PURCHASE, BARTER, EXPORTATION, AND IMPORTATION OF WILDLIFE AND PLANTS SEIZURE AND FORFEITURE PROCEDURES Disposal of Forfeited or Abandoned Property § 12.33 Disposal. (a) The Director shall...

R and D programme on radioactive waste disposal into geological formations (study of a clay formation)

International Nuclear Information System (INIS)

Centre d'Etude de l'Energie Nucleaire, Mol

1987-01-01

This report deals with the R and D activities performed by the Belgian Nuclear Research Establishment (SCK/CEN) and its subcontractors concerning the disposal of high-level and long-life conditioned wastes in a deep clay formation, the Boom clay. The studies reported concern equally experimental as theoretical work spread over the following research issues: geochemical characterization of the Boom clay, modelling of radionuclide migration in the clay environment, irradiation effects and corrosion behaviour of candidate canister materials in the Boom clay, geomechanical, construction, backfilling and sealing studies related to underground facilities, regional hydrological investigations of the Mol site and safety and risk analysis. The geomechanical and construction-related studies are to a large extent focused on in situ research, performed along the construction of the underground Hades laboratory. The corrosion studies are also dealing with the preparation of in situ experiments in the same underground laboratory. These various research issues are meant to contribute to the assessment of the technical feasibility and safety of the geological disposal in an argillaceous host formation

Development of technical information database for high level waste disposal

International Nuclear Information System (INIS)

Kudo, Koji; Takada, Susumu; Kawanishi, Motoi

2005-01-01

A concept design of the high level waste disposal information database and the disposal technologies information database are explained. The high level waste disposal information database contains information on technologies, waste, management and rules, R and D, each step of disposal site selection, characteristics of sites, demonstration of disposal technology, design of disposal site, application for disposal permit, construction of disposal site, operation and closing. Construction of the disposal technologies information system and the geological disposal technologies information system is described. The screen image of the geological disposal technologies information system is shown. User is able to search the full text retrieval and attribute retrieval in the image. (S.Y. )

Public acceptability of risk of radioactive waste disposal

International Nuclear Information System (INIS)

Millerd, W.H.

1977-01-01

A ''public interest'' viewpoint is presented on the disposal of radioactive wastes. Criteria for the development of disposal methods are needed. The current program to develop disposal sites and methods has become an experiment. The advantages and disadvantages of radwaste disposal as an ongoing experiment are discussed briefly

Alternatives for future land disposal of radioactive waste

International Nuclear Information System (INIS)

Mallory, C.W.

1982-01-01

Shallow land burial incorporating improvements to facilitate stabilization and decommissioning will continue to be the primary method of disposing of low level waste in areas where conditions are suitable for this type of disposal. The existing disposal sites should be closely monitored to assure that continued acceptance of this method of disposal. Plans for the decommissioning of the existing sites should be closely reviewed to assure that the planning is adequate and that adequate resources will be available to implement the decommissioning plan. For these areas where geological conditions are not suitable for shallow land burial and in situations where a higher degree of containment is desired, alternative disposal methods should be considered. Technology exists or is readily attainable to provide engineered disposal facilities which provide a higher degree of containment and can be readily decommissioned. The cost of disposal using these methods can be competitive with shallow land burial when the cost of environmental and hydrogeologic investigations and decommissioning are included. Disposal of radioactive waste having low activity in secure sanitary landfills could significantly reduce the transportation and disposal requirements for low level waste

FFTF disposable solid waste cask

Energy Technology Data Exchange (ETDEWEB)

Thomson, J. D.; Goetsch, S. D.

1983-01-01

Disposal of radioactive waste from the Fast Flux Test Facility (FFTF) will utilize a Disposable Solid Waste Cask (DSWC) for the transport and burial of irradiated stainless steel and inconel materials. Retrievability coupled with the desire for minimal facilities and labor costs at the disposal site identified the need for the DSWC. Design requirements for this system were patterned after Type B packages as outlined in 10 CFR 71 with a few exceptions based on site and payload requirements. A summary of the design basis, supporting analytical methods and fabrication practices developed to deploy the DSWC is provided in this paper.

FFTF disposable solid waste cask

International Nuclear Information System (INIS)

Thomson, J.D.; Goetsch, S.D.

1983-01-01

Disposal of radioactive waste from the Fast Flux Test Facility (FFTF) will utilize a Disposable Solid Waste Cask (DSWC) for the transport and burial of irradiated stainless steel and inconel materials. Retrievability coupled with the desire for minimal facilities and labor costs at the disposal site identified the need for the DSWC. Design requirements for this system were patterned after Type B packages as outlined in 10 CFR 71 with a few exceptions based on site and payload requirements. A summary of the design basis, supporting analytical methods and fabrication practices developed to deploy the DSWC is provided in this paper

Disposable bioprocessing: the future has arrived.

Science.gov (United States)

Rao, Govind; Moreira, Antonio; Brorson, Kurt

2009-02-01

Increasing cost pressures are driving the rapid adoption of disposables in bioprocessing. While well ensconced in lab-scale operations, the lower operating/ validation costs at larger scale and relative ease of use are leading to these systems entering all stages and operations of a typical biopharmaceutical manufacturing process. Here, we focus on progress made in the incorporation of disposable equipment with sensor technology in bioprocessing throughout the development cycle. We note that sensor patch technology is mostly being adapted to disposable cell culture devices, but future adaptation to downstream steps is conceivable. Lastly, regulatory requirements are also briefly assessed in the context of disposables and the Process Analytical Technologies (PAT) and Quality by Design (QbD) initiatives.

On-site disposal as a decommissioning strategy

International Nuclear Information System (INIS)

1999-11-01

On-site disposal is not a novel decommissioning strategy in the history of the nuclear industry. Several projects based on this strategy have been implemented. Moreover, a number of studies and proposals have explored variations within the strategy, ranging from in situ disposal of entire facilities or portions thereof to disposal within the site boundary of major components such as the reactor pressure vessel or steam generators. Regardless of these initiatives, and despite a significant potential for dose, radioactive waste and cost reduction, on-site disposal has often been disregarded as a viable decommissioning strategy, generally as the result of environmental and other public concerns. Little attention has been given to on-site disposal in previous IAEA publications in the field of decommissioning. The objective of this report is to establish an awareness of technical factors that may or may not favour the adoption of on-site disposal as a decommissioning strategy. In addition, this report presents an overview of relevant national experiences, studies and proposals. The expected end result is to show that, subject to safety and environmental protection assessment, on-site disposal can be a viable decommissioning option and should be taken into consideration in decision making

Review of the nuclear waste disposal problem

International Nuclear Information System (INIS)

Poch, L.A.; Wolsko, T.D.

1979-10-01

Regardless of future nuclear policy, a nuclear waste disposal problem does exist and must be dealt with. Even a moratorium on new nuclear plants leaves us with the wastes already in existence and wastes yet to be generated by reactors in operation. Thus, technologies to effectively dispose of our current waste problem must be researched and identified and, then, disposal facilities built. The magnitude of the waste disposal problem is a function of future nuclear policy. There are some waste disposal technologies that are suitable for both forms of HLW (spent fuel and reprocessing wastes), whereas others can be used with only reprocessed wastes. Therefore, the sooner a decision on the future of nuclear power is made the more accurately the magnitude of the waste problem will be known, thereby identifying those technologies that deserve more attention and funding. It is shown that there are risks associated with every disposal technology. One technology may afford a higher isolation potential at the expense of increased transportation risks in comparison to a second technology. Establishing the types of risks we are willing to live with must be resolved before any waste disposal technology can be instituted for widespread commercial use

Waste disposal technologies: designs and evaluations

International Nuclear Information System (INIS)

Shaw, R.A.

1987-01-01

Many states and compacts are presently in the throes of considering what technology to select for their low level waste disposal site. Both the technical and economic aspects of disposal technology are important considerations in these decisions. It is also important that they be considered in the context of the entire system. In the case of a nuclear power plant, that system encompasses the various individual waste streams that contain radioactivity, the processing equipment which reduces the volume and/or alters the form in which the radioisotopes are contained, the packaging of the processed wastes in shipment, and finally its disposal. One further part of this is the monitoring that takes place in all stages of this operation. This paper discusses the results of some research that has been sponsored by EPRI with the principal contractor being Rogers and Associates Engineering Corporation. Included is a description of the distinguishing features found in disposal technologies developed in a generic framework, designs for a selected set of these disposal technologies and the costs which have been derived from these designs. In addition, a description of the early efforts towards defining the performance of these various disposal technologies is described. 5 figures, 1 table

48 CFR 45.604-1 - Disposal methods.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Disposal methods. 45.604-1 Section 45.604-1 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Reutilization, and Disposal 45.604-1 Disposal methods. (a) Except as provided...

Pathway analysis for alternate low-level waste disposal methods

International Nuclear Information System (INIS)

Rao, R.R.; Kozak, M.W.; McCord, J.T.; Olague, N.E.

1992-01-01

The purpose of this paper is to evaluate a complete set of environmental pathways for disposal options and conditions that the Nuclear Regulatory Commission (NRC) may analyze for a low-level radioactive waste (LLW) license application. The regulations pertaining In the past, shallow-land burial has been used for the disposal of low-level radioactive waste. However, with the advent of the State Compact system of LLW disposal, many alternative technologies may be used. The alternative LLW disposal facilities include below- ground vault, tumulus, above-ground vault, shaft, and mine disposal This paper will form the foundation of an update of the previously developed Sandia National Laboratories (SNL)/NRC LLW performance assessment methodology. Based on the pathway assessment for alternative disposal methods, a determination will be made about whether the current methodology can satisfactorily analyze the pathways and phenomena likely to be important for the full range of potential disposal options. We have attempted to be conservative in keeping pathways in the lists that may usually be of marginal importance. In this way we can build confidence that we have spanned the range of cases likely to be encountered at a real site. Results of the pathway assessment indicate that disposal methods can be categorized in groupings based on their depth of disposal. For the deep disposal options of shaft and mine disposal, the key pathways are identical. The shallow disposal options, such as tumulus, shallow-land, and below-ground vault disposal also may be grouped together from a pathway analysis perspective. Above-ground vault disposal cannot be grouped with any of the other disposal options. The pathway analysis shows a definite trend concerning depth of disposal. The above-ground option has the largest number of significant pathways. As the waste becomes more isolated, the number of significant pathways is reduced. Similar to shallow-land burial, it was found that for all

Nuclear waste disposal in subseabed geologic formatons: the Seabed Disposal Program

International Nuclear Information System (INIS)

Anderson, D.R.

1979-05-01

The goal of the Seabed Disposal Program is to assess the technical and environmental feasibility of using geologic formations under the sea floor for the disposal of processed high-level radioactive wastes or repackaged spent reactor fuel. Studies are focused on the abyssal hill regions of the sea floors in the middle of tectonic plates and under massive surface current gyres. The red-clay sediments here are from 50 to 100 meters thick, are continuously depositional (without periods of erosion), and have been geologically and climatologically stable for millions of years. Mineral deposits and biological activity are minimal, and bottom currents are weak and variable. Five years of research have revealed no technological reason why nuclear waste disposal in these areas would be impractical. However, scientific assessment is not complete. Also, legal political, and sociological factors may well become the governing elements in such use of international waters. These factors are being examined as part of the work of the Seabed Working Group, an international adjunct of the Seabed Program, with members from France, England, Japan, Canada, and the United States

Nuclear waste disposal in subseabed geologic formatons: the Seabed Disposal Program

Energy Technology Data Exchange (ETDEWEB)

Anderson, D.R.

1979-05-01

The goal of the Seabed Disposal Program is to assess the technical and environmental feasibility of using geologic formations under the sea floor for the disposal of processed high-level radioactive wastes or repackaged spent reactor fuel. Studies are focused on the abyssal hill regions of the sea floors in the middle of tectonic plates and under massive surface current gyres. The red-clay sediments here are from 50 to 100 meters thick, are continuously depositional (without periods of erosion), and have been geologically and climatologically stable for millions of years. Mineral deposits and biological activity are minimal, and bottom currents are weak and variable. Five years of research have revealed no technological reason why nuclear waste disposal in these areas would be impractical. However, scientific assessment is not complete. Also, legal political, and sociological factors may well become the governing elements in such use of international waters. These factors are being examined as part of the work of the Seabed Working Group, an international adjunct of the Seabed Program, with members from France, England, Japan, Canada, and the United States.

Cement-Polymer Composite Containers for Radioactive Wastes Disposal

International Nuclear Information System (INIS)

Ghattas, N.K.; Eskander, S.B.; Bayoumi, T.A.; Saleh, H.M.

2009-01-01

Improving cement-composite containers using polymer as organic additives was studied extensively. Both unsaturated styrenated polyester (SPE) and polymethyl methacrylate (PMMA) were used to fill the pores in cement containers that used for disposal of radioactive wastes. Two different techniques were adopted for the addition of organic polymers based on their viscosity. The low density PMMA was added using impregnation technique. On the other hand high density SPE was mixed with cement paste as a premix process. Predetermined weight of dried borate radioactive powder waste simulate was introduced into the Cement-polymer composite (CPC) container and then closed before subjecting it to leaching characterization. The effect of the organic polymers on the hydration of cement matrix and on the properties of the obtained CPC container has been studied using X-ray diffraction, IR-analysis, thermal effects and weight loss. Porosity, pore parameters and rate of release were also determined. The results obtained showed that for the candidate CPC container positive effect of polymer dominates and an improvement in the retardation rate of PMMA release radionuclides was observed

Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: a case study in southern China.

Science.gov (United States)

Yi, Shuping; Ma, Haiyi; Zheng, Chunmiao; Zhu, Xiaobin; Wang, Hua'an; Li, Xueshan; Hu, Xueling; Qin, Jianbo

2012-01-01

Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world, particularly since a regional strategy for LILW disposal has been implemented to protect humans and the environment. This paper presents a demonstration of the site assessment process through a case study focusing mainly on the geologic, hydrogeologic and geochemical characteristics of the candidate site. A joint on-site and laboratory investigation, supplemented by numerical modeling, was implemented in this assessment. Results indicate that no fault is present in the site area, although there are some minor joints and fractures, primarily showing a north-south trend. Most of the joints are filled with quartz deposits and would thus function hydraulically as impervious barriers. Investigation of local hydrologic boundaries has shown that the candidate site represents an essentially isolated hydrogeologic unit, and that little or no groundwater flow occurs across its boundaries on the north or east, or across the hilly areas to the south. Groundwater in the site area is recharged by precipitation and discharges primarily by evapo-transpiration and surface flow through a narrow outlet to the west. Groundwater flows slowly from the hilly area to the foot of the hills and discharges mainly into the inner brooks and marshes. Some groundwater circulates in deeper granite in a slower manner. The vadose zone in the site was investigated specially for their significant capability for restraining the transport of radionuclides. Results indicate that the vadose zone is up to 38m in thickness and is made up of alluvial clay soils and very highly weathered granite. The vadose

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

International Nuclear Information System (INIS)

Farmer, J.C.; Van Konynenburg, R.A.; McCright, R.D.; Gdowski, G.E.

1988-05-01

Three copper-based alloys --- CDA 102 (OFHC copper), CDA 613 (aluminum bronze), and CDA 715 (Cu-30Ni) --- are being considered as possible materials for the fabrication of high-level radioactive-waste disposal containers. Waste will include fuel assemblies from reactors as well as borosilicate glass forms, and will be sent to the prospective repository at Yucca Mountain, Nevada, for emplacement. The three copper-based alloys discussed here are being considered in addition to the iron- to nickel-based austenitic materials discussed in Volume 3. The decay of radionuclides will result in substantial heat generation and in fluxes of gamma radiation. In this environment, container materials may degrade by atmospheric oxidation, uniform aqueous phase corrosion, pitting, crevice corrosion, transgranular stress corrosion cracking (TGSCC) in tarnishing environments, or intergranular stress corrosion cracking (IGSCC) in nontarnishing environments. This report is a critical survey of available data on the stress corrosion cracking (SCC) of the three copper-based alloys. The requisite conditions for TGSCC and IGSCC include combinations of stress, oxygen, ammonia or nitrite, and water. Note that nitrite is generated by gamma radiolysis of moisture films in air but that ammonia is not. TGSCC has been observed in CDA 102 and CDA 613 exposed to moist ammonia-containing environments whereas SCC has not been documented for CDA 715 under similar conditions. SCC is also promoted in copper by nitrite ions. Furthermore, phosphorus-deoxidized copper is unusually susceptible to embrittlement in such environments. The presence of tin in CDA 613 prevents IGSCC. It is believed that tin segregates to grain boundaries, where it oxidizes very slowly, thereby inhibiting the oxidation of aluminum. 117 refs., 27 figs., 9 tabs

Defense High Level Waste Disposal Container System Description Document

International Nuclear Information System (INIS)

2000-01-01

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials

Manufacture of disposal canisters

International Nuclear Information System (INIS)

Nolvi, L.

2009-12-01

The report summarizes the development work carried out in the manufacturing of disposal canister components, and present status, in readiness for manufacturing, of the components for use in assembly of spent nuclear fuel disposal canister. The disposal canister consist of two major components: the nodular graphite cast iron insert and overpack of oxygen-free copper. The manufacturing process for copper components begins with a cylindrical cast copper billet. Three different manufacturing processes i.e. pierce and draw, extrusion and forging are being developed, which produce a seamless copper tube or a tube with an integrated bottom. The pierce and draw process, Posiva's reference method, makes an integrated bottom possible and only the lid requires welding. Inserts for BWR-element are cast with 12 square channels and inserts for VVER 440-element with 12 round channels. Inserts for EPR-elements have four square channels. Casting of BWR insert type has been studied so far. Experience of casting inserts for PWR, which is similar to the EPR-type, has been got in co-operation with SKB. The report describes the processes being developed for manufacture of disposal canister components and some results of the manufacturing experiments are presented. Quality assurance and quality control in manufacture of canister component is described. (orig.)

21 CFR 880.6060 - Medical disposable bedding.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Medical disposable bedding. 880.6060 Section 880.6060 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED... Devices § 880.6060 Medical disposable bedding. (a) Identification. Medical disposable bedding is a device...

23 CFR 710.409 - Disposals.

Science.gov (United States)

2010-04-01

... 23 Highways 1 2010-04-01 2010-04-01 false Disposals. 710.409 Section 710.409 Highways FEDERAL HIGHWAY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RIGHT-OF-WAY AND ENVIRONMENT RIGHT-OF-WAY AND REAL ESTATE Real Property Management § 710.409 Disposals. (a) Real property interests determined to be excess...

Recent activity on disposal of uranium waste

International Nuclear Information System (INIS)

Fujiwara, Noboru

1999-01-01

The concept on the disposal of uranium waste has not been discussed in the Atomic Energy Commission of Japan, but the research and development of it are carried out in the company and agency which are related to uranium waste. In this paper, the present condition and problems on disposal of uranium waste were shown in aspect of the nuclear fuel manufacturing companies' activity. As main contents, the past circumstances on the disposal of uranium waste, the past activity of nuclear fuel manufacturing companies, outline and properties of uranium waste were shown, and ideas of nuclear fuel manufacturing companies on the disposal of uranium waste were reported with disposal idea in the long-term program for development and utilization of nuclear energy. (author)

41 CFR 102-75.280 - What information concerning a proposed disposal must a disposal agency provide to the Attorney...

Science.gov (United States)

2010-07-01

... applicability of antitrust laws? 102-75.280 Section 102-75.280 Public Contracts and Property Management Federal... PROPERTY DISPOSAL Surplus Real Property Disposal Applicability of Antitrust Laws § 102-75.280 What... the applicability of antitrust laws? The disposal agency must promptly provide the Attorney General...

Radwaste characteristics and Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

Sung, Suk Hyun; Jeong, Yi Yeong; Kim, Ki Hong

2008-01-01

The purpose of Radioactive Waste Acceptance Criteria (WAC) is to verify a radioactive waste compliance with radioactive disposal facility requirements in order to maintain a disposal facility's performance objectives and to ensure its safety. To develop WAC which is conformable with domestic disposal site conditions, we furthermore analysed the WAC of foreign disposal sites similar to the Kyung-Ju disposal site and the characteristics of various wastes which are being generated from Korea nuclear facilities. Radioactive WAC was developed in the technical cooperation with the Korea Atomic Energy Research Institute in consideration of characteristics of the wastes which are being generated from various facilities, waste generators' opinions and other conditions. The established criteria was also discussed and verified at an advisory committee which was comprised of some experts from universities, institutes and the industry. So radioactive WAC was developed to accept all wastes which are being generated from various nuclear facilities as much as possible, ensuring the safety of a disposal facility. But this developed waste acceptance criteria is not a criteria to accept all the present wastes generated from various nuclear facilities, so waste generators must seek an alternative treatment method for wastes which were not worth disposing of, and then they must treat the wastes more to be acceptable at a disposal site. The radioactive disposal facility WAC will continuously complement certain criteria related to a disposal concentration limit for individual radionuclide in order to ensure a long-term safety.

Disposal Of Waste Matter

International Nuclear Information System (INIS)

Kim, Jeong Hyeon; Lee, Seung Mu

1989-02-01

This book deals with disposal of waste matter management of soiled waste matter in city with introduction, definition of waste matter, meaning of management of waste matter, management system of waste matter, current condition in the country, collect and transportation of waste matter disposal liquid waste matter, industrial waste matter like plastic, waste gas sludge, pulp and sulfuric acid, recycling technology of waste matter such as recycling system of Black clawson, Monroe and Rome.

The partnership experience on the disposal of low- and intermediate-level short-lived waste in Belgium

International Nuclear Information System (INIS)

Preter, P. de; Cool, W.; Hooft, E.; Waffelaert, A.; Blommaert, J.; Draulans, J.

2008-01-01

With the governmental decision of January 16, 1998, the long-term storage option for the low- and intermediate-level short-lived waste (category A waste) was abandoned and ONDRAF/NIRAS was given the mission to further examine the options of deep and surface disposal, in order to prepare a federal decision on the technical option to be developed. ONDRAF/NIRAS was also asked to develop the methods and structures of interaction with the local stakeholders, and to limit its siting activities to nuclear and candidate municipalities. This brought ONDRAF/NIRAS to the concept of local partnerships with interested municipalities, and during the pre-project phase 1998-2006 partnerships were created with the municipalities of Dessel (STOLA-Dessel, 1999), Mol (MONA, 2000) and Fleurus-Farciennes (PaLoFF, 2003). On 23 June, 2006 the Belgian Government decided that category A waste will be disposed of in a near-surface repository on the territory of the Dessel municipality. This decision implies that ONDRAF/NIRAS, in further interaction with the local stakeholders, can start the preparation of a licence application. This decision was the endpoint of the pre-project phase (1998-2006) and was based on the final reports of the partnerships of Dessel (STOLA-Dessel, now STORA) and Mol (MONA), approved by their municipality councils, and on ONDRAF/NIRAS final report, confirming the feasibility of the proposed disposal systems. As the municipality council of Fleurus did not approve the final report of the partnership PaLoFF, ONDRAF/NIRAS did not submit this report to the responsible minister. The preceding positive local decision in both Dessel (May 2005) and Mol (July 2005), and both on the partnership and municipality council level, to accept, under certain conditions, a disposal facility on their territory was the result of a 6 years long process of discussions within the partnership of all aspects of the disposal system and its integration in the municipality. During these

Specified radioactive waste final disposal act

International Nuclear Information System (INIS)

Yasui, Masaya

2001-01-01

Radioactive wastes must be finally and safely disposed far from human activities. Disposal act is a long-range task and needs to be understood and accepted by public for site selection. This paper explains basic policy of Japanese Government for final disposal act of specified radioactive wastes, examination for site selection guidelines to promote residential understanding, general concept of multi-barrier system for isolating the specific radioactive wastes, and research and technical development for radioactive waste management. (S. Ohno)

Radioactive wastes storage and disposal. Chapter 8

International Nuclear Information System (INIS)

2002-01-01

The Chapter 8 is essentially dedicated to radioactive waste management - storage and disposal. The management safety is being provided due to packages and facilities of waste disposal and storage. It is noted that at selection of sites for waste disposal it is necessary account rock properties and ways of the wastes delivery pathways

Nuclear waste management: storage and disposal aspects

International Nuclear Information System (INIS)

Patterson, B.D.; Dave, S.A.; O'Connell, W.J.

1980-01-01

Long-term disposal of nuclear wastes must resolve difficulties arising chiefly from the potential for contamination of the environment and the risk of misuse. Alternatives available for storage and disposal of wastes are examined in this overview paper. Guidelines and criteria which may govern in the development of methods of disposal are discussed

Environment impact of a very low level waste specific landfill

International Nuclear Information System (INIS)

Brun-Yaba, C.; Peres, J.M.; Besnus, F.

1996-01-01

Operating enrichment plants, nuclear power plants and reprocessing plants and the decommissioning of nuclear facilities will give rise to large volumes of waste material (concrete, steel and others metals, technological wastes heat insulators...) and most of them, in term of quantities, will be categorized as very low level wastes. This paper deals with the environmental impact of a specific landfill as a final destination for the very low level radioactive waste (VLLW) with the aim of providing technical elements for safer workers practices during the operational and the monitoring phases and for a public occupation after closure of the site. This study has been made on the basis of inventories in terms of estimated quantities and spectra of the French VLLW for a set of scenarios which are representative of practices in a landfill. (author)

Operational technology for greater confinement disposal

International Nuclear Information System (INIS)

Dickman, P.T.; Vollmer, A.T.; Hunter, P.H.

1984-12-01

Procedures and methods for the design and operation of a greater confinement disposal facility using large-diameter boreholes are discussed. It is assumed that the facility would be located at an operating low-level waste disposal site and that only a small portion of the wastes received at the site would require greater confinement disposal. The document is organized into sections addressing: facility planning process; facility construction; waste loading and handling; radiological safety planning; operations procedures; and engineering cost studies. While primarily written for low-level waste management site operators and managers, a detailed economic assessment section is included that should assist planners in performing cost analyses. Economic assessments for both commercial and US government greater confinement disposal facilities are included. The estimated disposal costs range from $27 to $104 per cubic foot for a commercial facility and from $17 to $60 per cubic foot for a government facility. These costs are based on average site preparation, construction, and waste loading costs for both contact- and remote-handled wastes. 14 figures, 22 tables

DOE's planning process for mixed low-level waste disposal

International Nuclear Information System (INIS)

Case, J.T.; Letourneau, M.J.; Chu, M.S.Y.

1995-01-01

A disposal planning process was established by the Department of Energy (DOE) Mixed Low-Level Waste (MLLW) Disposal Workgroup. The process, jointly developed with the States, includes three steps: site-screening, site-evaluation, and configuration study. As a result of the screening process, 28 sites have been eliminated from further consideration for MLLW disposal and 4 sites have been assigned a lower priority for evaluation. Currently 16 sites are being evaluated by the DOE for their potential strengths and weaknesses as MLLW disposal sites. The results of the evaluation will provide a general idea of the technical capability of the 16 disposal sites; the results can also be used to identify which treated MLLW streams can be disposed on-site and which should be disposed of off-site. The information will then serve as the basis for a disposal configuration study, which includes analysis of both technical as well as non-technical issues, that will lead to the ultimate decision on MLLW disposal site locations

The disposal of radioactive waste on land

Energy Technology Data Exchange (ETDEWEB)

None

1957-09-01

A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

Hanford grout disposal program - an environmentally sound alternative

International Nuclear Information System (INIS)

Bergman, T.B.; Allison, J.M.

1987-01-01

The Hanford Grout Disposal Program (HGDP) is a comprehensive, integrated program to develop technology and facilities for the disposal of ∼ 3.0 x 10 5 m 3 (80 million gal) of the low-level fraction of liquid radioactive tank wastes at the Hanford site in southeastern Washington state. Environmentally sound disposal via long-term protection of the public and the environment is the principal goal of the HGDP. To accomplish this goal, several criteria have been established that guide technology and facility development activities. The key criteria are discussed. To meet the challenges posed by disposal of these wastes, the HGDP is developing a waste form using grout-forming materials, such as blast furnace slag, fly ash, clays, and Portland cement for solidification and immobilization of both the radioactive and hazardous chemical constituents. In addition to development of a final waste form, the HGDP is also developing a unique disposal system to assure long-term protection of the public and the environment. Disposal of a low-level nonhazardous waste will be initiated, as a demonstration of the disposal system concept, in June 1988. Disposal of higher activity hazardous wastes is scheduled to begin in October 1989

Offshore disposal of oil-based drilling fluid waste

International Nuclear Information System (INIS)

Malachosky, E.; Shannon, B.E.; Jackson, J.E.

1991-01-01

Offshore drilling operations in the Gulf of Mexico may use oil-based drilling fluids to mitigate drilling problems. The result is the generation of a significant quantity of oily cuttings and mud. The transportation of this waste for onshore disposal is a concern from a standpoint of both personnel safety and potential environmental impact. A process for preparing a slurry of this waste and the subsequent disposal of the slurry through annular pumping has been put into use by ARCO Oil and Gas Company. The disposal technique has been approved by the Minerals Management Service (MMS). The slurried waste is displaced down a casing annulus into a permeable zone at a depth below the surface casing setting depth. The annular disposal includes all cuttings and waste oil mud generated during drilling with oil-based fluids. This disposal technique negates the need for cuttings storage on the platform, transportation to shore, and the environmental effects of onshore surface disposal. The paper describes the environmental and safety concerns with onshore disposal, the benefits of annular disposal, and the equipment and process used for the preparation and pumping of the slurry

Radioactive waste disposal and political aspects

International Nuclear Information System (INIS)

Blanc, M.

1992-01-01

The difficulties presented by the current atomic energy law for the nuclear waste disposal in Switzerland are shown. It is emphasised how important scientific information is in the political solutions for nuclear disposal

Concept for Underground Disposal of Nuclear Waste

Science.gov (United States)

Bowyer, J. M.

1987-01-01

Packaged waste placed in empty oil-shale mines. Concept for disposal of nuclear waste economically synergistic with earlier proposal concerning backfilling of oil-shale mines. New disposal concept superior to earlier schemes for disposal in hard-rock and salt mines because less uncertainty about ability of oil-shale mine to contain waste safely for millenium.

Disposal facility data for the interim performance

International Nuclear Information System (INIS)

Eiholzer, C.R.

1995-01-01

The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

Shallow land disposal technology

Energy Technology Data Exchange (ETDEWEB)

Pillette-Cousin, L. [Nuclear Environment Technology Insitute, Taejon (Korea, Republic of Korea )

1997-12-31

This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L`Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs.

Shallow land disposal technology

International Nuclear Information System (INIS)

Pillette-Cousin, L.

1997-01-01

This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L'Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs

General criteria for radioactive waste disposal

International Nuclear Information System (INIS)

Maxey, M.N.; Musgrave, B.C.; Watkins, G.B.

1979-01-01

Techniques are being developed for conversion of radioactive wastes to solids and their placement into repositories. Criteria for such disposal are needed to assure protection of the biosphere. The ALARA (as low as reasonably achievable) principle should be applicable at all times during the disposal period. Radioactive wastes can be categorized into three classes, depending on the activity. Three approaches were developed for judging the adequacy of disposal concepts: acceptable risk, ore body comparison, and three-stage ore body comparison

Commercial mixed waste treatment and disposal

International Nuclear Information System (INIS)

Vance, J.K.

1994-01-01

At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

Canister materials proposed for final disposal of high level nuclear waste - a review with respect to corrosion resistance

Energy Technology Data Exchange (ETDEWEB)

Mattsson, E; Odoj, R; Merz, E [eds.

1981-06-01

Spent fuel from nuclear reactors has to be disposed of either after reprocessing or without such treatment. Due to toxic radiation the nuclear waste has to be isolated from the biosphere for 300-1000 years, or in extreme cases for more than 100,000 years. The nuclear waste will be enclosed in corrosion resistant canisters. These will be deposited in repositories in geological formations, such as granite, basalt, clay, bedded or domed salt, or the sediments beneath the deep ocean floor. There the canisters will be exposed to groundwater, brine or seawater at an elevated temperature. Species formed by radiolysis may affect the corrosivity of the agent. The corrosion resistance of candidate canister materials is evaluated by corrosion tests and by thermodynamic and mass transport calculations. Examination of ancient metal objects after long exposure in nature may give additional information. On the basis of the work carried out so far, the principal candidate canister materials are titanium materials, copper and high purity alumina.

Reversible deep disposal

International Nuclear Information System (INIS)

2009-10-01

This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of October 8, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the concept of deep reversible disposal for high level/long living radioactive wastes, as considered by the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The document presents the social and political reasons of reversibility, the technical means considered (containers, disposal cavities, monitoring system, test facilities and industrial prototypes), the decisional process (progressive development and blocked off of the facility, public information and debate). (J.S.)

Timing of High-level Waste Disposal

International Nuclear Information System (INIS)

2008-01-01

This study identifies key factors influencing the timing of high-level waste (HLW) disposal and examines how social acceptability, technical soundness, environmental responsibility and economic feasibility impact on national strategies for HLW management and disposal. Based on case study analyses, it also presents the strategic approaches adopted in a number of national policies to address public concerns and civil society requirements regarding long-term stewardship of high-level radioactive waste. The findings and conclusions of the study confirm the importance of informing all stakeholders and involving them in the decision-making process in order to implement HLW disposal strategies successfully. This study will be of considerable interest to nuclear energy policy makers and analysts as well as to experts in the area of radioactive waste management and disposal. (author)

2005 dossier: granite. Tome: architecture and management of the geologic disposal

International Nuclear Information System (INIS)

2005-01-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the geologic disposal of high-level and long-lived radioactive wastes in granite formations. Content: 1 - Approach of the study: main steps since the December 30, 1991 law, ANDRA's research program on disposal in granitic formations; 2 - high-level and long-lived (HLLL) wastes: production scenarios, waste categories, inventory model; 3 - disposal facility design in granitic environment: definition of the geologic disposal functions, the granitic material, general facility design options; 4 - general architecture of a disposal facility in granitic environment: surface facilities, underground facilities, disposal process, operational safety; 5 - B-type wastes disposal area: primary containers of B-type wastes, safety options, concrete containers, disposal alveoles, architecture of the B-type wastes disposal area, disposal process and feasibility aspects, functions of disposal components with time; 6 - C-type wastes disposal area: C-type wastes primary containers, safety options, super-containers, disposal alveoles, architecture of the C-type wastes disposal area, disposal process in a reversibility logics, functions of disposal components with time; 7 - spent fuels disposal area: spent fuel assemblies, safety options, spent fuel containers, disposal alveoles, architecture of the spent fuel disposal area, disposal process in a reversibility logics, functions of disposal components with time; 8 - conclusions: suitability of the architecture with various types of French granites, strong design, reversibility taken into consideration. (J.S.)

Low-level-waste-disposal methodologies

International Nuclear Information System (INIS)

Wheeler, M.L.; Dragonette, K.

1981-01-01

This report covers the followng: (1) history of low level waste disposal; (2) current practice at the five major DOE burial sites and six commercial sites with dominant features of these sites and radionuclide content of major waste types summarized in tables; (3) site performance with performance record on burial sites tabulated; and (4) proposed solutions. Shallow burial of low level waste is a continuously evolving practice, and each site has developed its own solutions to the handling and disposal of unusual waste forms. There are no existing national standards for such disposal. However, improvements in the methodology for low level waste disposal are occurring on several fronts. Standardized criteria are being developed by both the Nuclear Regulatory Commission (NRC) and by DOE. Improved techniques for shallow burial are evolving at both commercial and DOE facilities, as well as through research sponsored by NRC, DOE, and the Environmental Protection Agency. Alternatives to shallow burial, such as deeper burial or the use of mined cavities is also being investigated by DOE

48 CFR 245.603 - Disposal methods.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Disposal methods. 245.603 Section 245.603 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT... Contractor Inventory 245.603 Disposal methods. ...

Waste Disposal

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; B-Verstricht, J.; Van Iseghem, P.; Buyens, M.

1998-01-01

This contribution describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 1997 in three topical areas are reported on: performance assessments, waste forms/packages and near-and far field studies

Waste disposal into the ground

Energy Technology Data Exchange (ETDEWEB)

Mawson, C A

1955-07-01

The establishment of an atomic energy project is soon followed by the production of a variety of radioactive wastes which must be disposed of safely, quickly and cheaply. Experience has shown that much more thought has been devoted to the design of plant and laboratories than to the apparently dull problem of what to do with the wastes, but the nature of the wastes which will arise from nuclear power production calls for a change in this situation. We shall not be concerned here with power pile wastes, but disposal problems which have occurred in operation of experimental reactors have been serious enough to show that waste disposal should be considered during the early planning stages. (author)

Underground radioactive waste disposal concept

International Nuclear Information System (INIS)

Frgic, L.; Tor, K.; Hudec, M.

2002-01-01

The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

Chemical Stockpile Disposal Program

Energy Technology Data Exchange (ETDEWEB)

Krummel, J.R.; Policastro, A.J.; Olshansky, S.J.; McGinnis, L.D.

1990-10-01

As part of the Chemical Stockpile Disposal Program mandated by Public Law 99--145 (Department of Defense Authorization Act), an independent review is presented of the US Army Phase I environmental report for the disposal program at the Umatilla Depot Activity (UMDA) in Hermiston, Oregon. The Phase I report addressed new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). Those concerns were addressed by examining site-specific data for the Umatilla Depot Activity and by recommending the scope and content of a more detailed site-specific study. This independent review evaluates whether the new site-specific data presented in the Phase I report would alter the decision in favor of on-site disposal that was reached in the FPEIS, and whether the recommendations for the scope and content of the site-specific study are adequate. Based on the methods and assumptions presented in the FPEIS, the inclusion of more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at UMDA). It is recommended that alternative assumptions about meteorological conditions be considered and that site-specific data on water, ecological, socioeconomic, and cultural resources; seismicity; and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process. 7 refs., 1 fig.

Revised user's guide to the 'DISPOSALS' model

International Nuclear Information System (INIS)

Laundy, R.S.; James, A.R.; Groom, M.S.; LeJeune, S.R.

1985-04-01

This report provides a User's Guide to the 'DISPOSALS' computer model and includes instructions on how to set up and run a specific problem together with details of the scope, theoretical basis, data requirements and capabilities of the model. The function of the 'DISPOSALS' model is to make assignments of nuclear waste material in an optimum manner to a number of disposal sites each subject to a number of constraints such as limits on the volume and activity. The user is able to vary the number of disposal sites, the range and limits of the constraints to be applied to each disposal site and the objective function for optimisation. The model is based on the Linear Programming technique and uses CAP Scientific's LAMPS and MAGIC packages. Currently the model has been implemented on CAP Scientific's VAX 11/750 minicomputer. (author)

Melter Disposal Strategic Planning Document

Energy Technology Data Exchange (ETDEWEB)

BURBANK, D.A.

2000-09-25

This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

Safe disposal of radioactive wastes

International Nuclear Information System (INIS)

Hooker, P.; Metcalfe, R.; Milodowski, T.; Holliday, D.

1997-01-01

A high degree of international cooperation has characterized the two studies reported here which aim to address whether radioactive waste can be disposed of safely. Using hydrogeochemical and mineralogical surveying techniques earth scientists from the British Geological Survey have sought to identify and characterise suitable disposal sites. Aspects of the studies are explored emphasising their cooperative nature. (UK)

The AMES Laboratory chemical disposal site removal action: Source removal, processing, and disposal

International Nuclear Information System (INIS)

Shirley, R.S.

1996-01-01

The Ames Laboratory has historically supported the U.S. Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, chemical wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the U.S. Army Corps of Engineers (USACE), OHM Remediation Services Corp (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

The Ames Laboratory Chemical Disposal Site removal action: Source removal, processing, and disposal

International Nuclear Information System (INIS)

Shirley, R.S.

1995-01-01

The Ames Laboratory has historically supported the US Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, mixed wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the US Army Corps of Engineers (USACE), OHM Remediation Services Corp. (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

Nuclear waste disposal technology for Pacific Basin countries

International Nuclear Information System (INIS)

Langley, R.A. Jr.; Brothers, G.W.

1981-01-01

Safe long-term disposal of nuclear wastes is technically feasible. Further technological development offers the promise of reduced costs through elimination of unnecessary conservatism and redundance in waste disposal systems. The principal deterrents to waste disposal are social and political. The issues of nuclear waste storage and disposal are being confronted by many nuclear power countries including some of the Pacific Basin nuclear countries. Both mined geologic and subseabed disposal schemes are being developed actively. The countries of the Pacific Basin, because of their geographic proximity, could benefit by jointly planning their waste disposal activities. A single repository, of a design currently being considered, could hold all the estimated reprocessing waste from all the Pacific Basin countries past the year 2010. As a start, multinational review of alterntive disposal schemes would be beneficial. This review should include the subseabed disposal of radwastes. A multinational review of radwaste packaging is also suggested. Packages destined for a common repository, even though they may come from several countries, should be standardized to maximize repository efficiency and minimize operator exposure. Since package designs may be developed before finalization of a repository scheme and design, the packages should not have characteristics that would preclude or adversely affect operation of desirable repository options. The sociopolitical problems of waste disposal are a major deterrent to a multinational approach to waste disposal. The elected representatives of a given political entity have generally been reluctant to accept the waste from another political entity. Initial studies would, nevertheless, be beneficial either to a common solution to the problem, or to aid in separate solutions

Status on disposal of greater-than-Class C

Energy Technology Data Exchange (ETDEWEB)

Plummer, T.L.

1995-12-31

The Department of Energy (DOE) has developed a plan for the management and disposal of commercially generated greater-than-Class C (GTCC) low-level radioactive waste. The Low-Level Radioactive Waste Policy Amendments Act of 1985 made DOE responsible for disposal of GTCC waste. The act requires that GTCC waste be disposed in a Nuclear Regulatory Commission (NRC)-licensed facility. The NRC has amended 10 CFR 61 to express a preference for geologic disposal of GTCC waste. Based on reassessment studies, legislative guidance, and stakeholder involvement, a revised plan has been formulated to provide for total management of GTCC waste. The plan has four major thrusts: (1) plan for GTCC waste storage at the generator site until disposal is available, (2) establish storage for GTCC sealed sources posing health and safety risk to the public, (3) facilitate storage for other GTCC waste posing health and safety risk to the public, and (4) plan for co-disposal of GTCC waste in a geologic disposal site with similar waste types. The revised plan focuses on applying available resources to near- and long-term needs.

Criteria for high-level waste disposal

International Nuclear Information System (INIS)

Sousselier, Y.

1981-01-01

Disposal of radioactive wastes is storage without the intention of retrieval. But in such storage, it may be useful and in some cases necessary to have the possibility of retrieval at least for a certain period of time. In order to propose some criteria for HLW disposal, one has to examine how this basic concept is to be applied. HLW is waste separated as a raffinate in the first cycle of solvent extraction in reprocessing. Such waste contains the bulk of fission products which have long half lives, therefore the safety of a disposal site, at least after a certain period of time, must be intrinsic, i.e. not based on human intervention. There is a consensus that such a disposal is feasible in a suitable geological formation in which the integrity of the container will be reinforced by several additional barriers. Criteria for disposal can be proposed for all aspects of the question. The author discusses the aims of the safety analysis, particularly the length of time for this analysis, and the acceptable dose commitments resulting from the release of radionuclides, the number and role of each barrier, and a holistic analysis of safety external factors. (Auth.)

Waste and Disposal: Demonstration

International Nuclear Information System (INIS)

Neerdael, B.; Buyens, M.; De Bruyn, D.; Volckaert, G.

2002-01-01

Within the Belgian R and D programme on geological disposal, demonstration experiments have become increasingly important. In this contribution to the scientific report 2001, an overview is given of SCK-CEN's activities and achievements in the field of large-scale demonstration experiments. In 2001, main emphasis was on the PRACLAY project, which is a large-scale experiment to demonstrate the construction and the operation of a gallery for the disposal of HLW in a clay formation. The PRACLAY experiment will contribute to enhance understanding of water flow and mass transport in dense clay-based materials as well as to improve the design of the reference disposal concept. In the context of PRACLAY, a surface experiment (OPHELIE) has been developed to prepare and to complement PRACLAY-related experimental work in the HADES Underground Research Laboratory. In 2001, efforts were focussed on the operation of the OPHELIE mock-up. SCK-CEN also contributed to the SELFRAC roject which studies the self-healing of fractures in a clay formation

Are Disposable and Standard Gonioscopy Lenses Comparable?

Science.gov (United States)

Lee, Bonny; Szirth, Bernard C; Fechtner, Robert D; Khouri, Albert S

2017-04-01

Gonioscopy is important in the evaluation and treatment of glaucoma. With increased scrutiny of acceptable sterilization processes for health care instruments, disposable gonioscopy lenses have recently been introduced. Single-time use lenses are theorized to decrease infection risk and eliminate the issue of wear and tear seen on standard, reusable lenses. However, patient care would be compromised if the quality of images produced by the disposable lens were inferior to those produced by the reusable lens. The purpose of this study was to compare the quality of images produced by disposable versus standard gonioscopy lenses. A disposable single mirror lens (Sensor Medical Technology) and a standard Volk G-1 gonioscopy lens were used to image 21 volunteers who were prospectively recruited for the study. Images of the inferior and temporal angles of each subject's left eye were acquired using a slit-lamp camera through the disposable and standard gonioscopy lens. In total, 74 images were graded using the Spaeth gonioscopic system and for clarity and quality. Clarity was scored as 1 or 2 and defined as either (1) all structures perceived or (2) all structures not perceived. Quality was scored as 1, 2, or 3, and defined as (1) all angle landmarks clear and well focused, (2) some angle landmarks clear, others blurred, or (3) angle landmarks could not be ascertained. The 74 images were divided into images taken with the disposable single mirror lens and images taken with the standard Volk G-1 gonioscopy lens. The clarity and quality scores for each of these 2 image groups were averaged and P-values were calculated. Average quality of images produced with the standard lens was 1.46±0.56 compared with 1.54±0.61 for those produced with the disposable lens (P=0.55). Average clarity of images produced with the standard lens was 1.47±0.51 compared with 1.49±0.51 (P=0.90) with the disposable lens. We conclude that there is no significant difference in quality of images

Scoping survey of perceived concerns, issues, and problems for near-surface disposal of FUSRAP waste

International Nuclear Information System (INIS)

Robinson, J.E.; Gilbert, T.L.

1982-12-01

This report is a scoping summary of concerns, issues, and perceived problems for near-surface disposal of radioactive waste, based on a survey of the current literature. Near-surface disposal means land burial in or within 15 to 20 m of the earth's surface. It includes shallow land burial (burial in trenches, typically about 6 m deep with a 2-m cap and cover) and some intermediate-depth land burial (e.g., trenches and cap similar to shallow land burial, but placed below 10 to 15 m of clean soil). Proposed solutions to anticipated problems also are discussed. The purpose of the report is to provide a better basis for identifying and evaluating the environmental impacts and related factors that must be analyzed and compared in assessing candidate near-surface disposal sites for FUSRAP waste. FUSRAP wastes are of diverse types, and their classification for regulatory purposes is not yet fixed. Most of it may be characterized as low-activity bulk solid waste, and is similar to mill tailings, but with somewhat lower average specific activity. It may also qualify as Class A segregated waste under the proposed 10 CFR 61 rules, but the parent radionuclides of concern in FUSRAP (primarily U-238 and Th-232) have longer half-lives than do the radionuclides of concern in most low-level waste. Most of the references reviewed deal with low-level waste or mill tailings, since there is as yet very little literature in the public domain on FUSRAP per se

DSEM, Radioactive Waste Disposal Site Economic Model

International Nuclear Information System (INIS)

Smith, P.R.

2005-01-01

1 - Description of program or function: The Disposal Site Economic Model calculates the average generator price, or average price per cubic foot charged by a disposal facility to a waste generator, one measure of comparing the economic attractiveness of different waste disposal site and disposal technology combinations. The generator price is calculated to recover all costs necessary to develop, construct, operate, close, and care for a site through the end of the institutional care period and to provide the necessary financial returns to the site developer and lender (when used). Six alternative disposal technologies, based on either private or public financing, can be considered - shallow land disposal, intermediate depth disposal, above or below ground vaults, modular concrete canister disposal, and earth mounded concrete bunkers - based on either private or public development. 2 - Method of solution: The economic models incorporate default cost data from the Conceptual Design Report (DOE/LLW-60T, June 1987), a study by Rodgers Associates Engineering Corporation. Because all costs are in constant 1986 dollars, the figures must be modified to account for inflation. Interest during construction is either capitalized for the private developer or rolled into the loan for the public developer. All capital costs during construction are depreciated over the operation life of the site using straight-line depreciation for the private sector. 3 - Restrictions on the complexity of the problem: Maxima of - 100 years post-operating period, 30 years operating period, 15 years pre-operating period. The model should be used with caution outside the range of 1.8 to 10.5 million cubic feet of total volume. Depreciation is not recognized with public development

Operation for Rokkasho Low Level Radioactive Waste Disposal Center

International Nuclear Information System (INIS)

Kamizono, Hideki

2008-01-01

The Rokkasho Low Level Radioactive Waste (LLW) Disposal Center is located in Oishitai, Rokkasho-mura, Kamikitagun, of Aomori Prefecture. This district is situated in the southern part of Shimohita Peninsula in the northeastern corner of the prefecture, which lies at the northern tip of Honshu, Japan's main island. The Rokkasho LLW Disposal Center deals with only LLW generated by operating of nuclear power plants. The No.1 and No.2 disposal facility are now in operation. The disposal facilities in operation have a total dispose capacity of 80,000m 3 (equivalent to 400,000 drums). Our final business scope is to dispose of radioactive waste corresponding to 600,000 m 3 (equivalent to 3000,000 drums). For No.1 disposal facility, we have been disposing of homogeneous waste, including condensed liquid waste, spent resin, solidified with cement and asphalt, etc. For No.2 disposal facility, we can bury a solid waste solidified with mortar, such as activated metals and plastics, etc. Using an improved construction technology for an artificial barrier, the concrete pits in No.2 disposal facility could be constructed more economical and spacious than that of No.1. Both No.1 and No.2 facility will be able to bury about 200,000 waste packages (drums) each corresponding to 40,000 m 3 . As of March 17, 2008, Approximately 200,00 waste drums summing up No.1 and No.2 disposal facility have been received from Nuclear power plants and buried. (author)

Stability of disposal rooms during waste retrieval

International Nuclear Information System (INIS)

Brandshaug, T.

1989-03-01

This report presents the results of a numerical analysis to determine the stability of waste disposal rooms for vertical and horizontal emplacement during the period of waste retrieval. It is assumed that waste retrieval starts 50 years after the initial emplacement of the waste, and that access to and retrieval of the waste containers take place through the disposal rooms. It is further assumed that the disposal rooms are not back-filled. Convective cooling of the disposal rooms in preparation for waste retrieval is included in the analysis. Conditions and parameters used were taken from the Nevada Nuclear Waste Storage Investigation (NNWSI) Project Site Characterization Plan Conceptual Design Report (MacDougall et al., 1987). Thermal results are presented which illustrate the heat transfer response of the rock adjacent to the disposal rooms. Mechanical results are presented which illustrate the predicted distribution of stress, joint slip, and room deformations for the period of time investigated. Under the assumption that the host rock can be classified as ''fair to good'' using the Geomechanics Classification System (Bieniawski, 1974), only light ground support would appear to be necessary for the disposal rooms to remain stable. 23 refs., 28 figs., 2 tabs

Cost effective disposal of whey

Energy Technology Data Exchange (ETDEWEB)

Zall, R R

1980-01-01

Means of reducing the problem of whey disposal are dealt with, covering inter alia the pre-treatment of cheese milk e.g., by ultrafiltration to lower the whey output, utilization of whey constituents, use of liquid whey for feeding, fermenting whey to produce methane and alcohol, and disposal of whey by irrigation of land or by purification in sewage treatment plants.

Argentina's radioactive waste disposal policy

International Nuclear Information System (INIS)

Palacios, E.

1986-01-01

The Argentina policy for radioactive waste disposal from nuclear facilities is presented. The radioactive wastes are treated and disposed in confinement systems which ensure the isolation of the radionucles for an appropriate period. The safety criteria adopted by Argentina Authorities in case of the release of radioactive materials under normal conditions and in case of accidents are analysed. (M.C.K.) [pt

Depleted uranium disposal options evaluation

International Nuclear Information System (INIS)

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D.

1994-05-01

The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ''waste,'' but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity

Verification and validation for waste disposal models

International Nuclear Information System (INIS)

1987-07-01

A set of evaluation criteria has been developed to assess the suitability of current verification and validation techniques for waste disposal methods. A survey of current practices and techniques was undertaken and evaluated using these criteria with the items most relevant to waste disposal models being identified. Recommendations regarding the most suitable verification and validation practices for nuclear waste disposal modelling software have been made

A new procedure for deep sea mining tailings disposal

OpenAIRE

Ma, W.; Schott, D.L.; Lodewijks, G.

2017-01-01

Deep sea mining tailings disposal is a new environmental challenge related to water pollution, mineral crust waste handling, and ocean biology. The objective of this paper is to propose a new tailings disposal procedure for the deep sea mining industry. Through comparisons of the tailings disposal methods which exist in on-land mining and the coastal mining fields, a new tailings disposal procedure, i.e., the submarine–backfill–dam–reuse (SBDR) tailings disposal procedure, is proposed. It com...

Panel session: Disposal of HLW - ready for implementation

International Nuclear Information System (INIS)

Heremans, R.; Come, B.; Barbreau, A.; Girardi, F.

1986-01-01

The paper is a report of a panel session at the European Community conference on radioactive waste management and disposal, Luxembourg 1985, concerning the safe and long-term disposal of high-activity and long-lived waste. The subjects discussed include: geological barriers including deep sea-bed sediments, engineered barriers, technological problems (repository construction, waste emplacement, backfilling and sealing), safety analysis, performance assessment of disposal system components, and finally institutional, legal and financial aspects of geological disposal. (U.K.)

Daily disposable contact lens prescribing around the world.

Science.gov (United States)

Efron, Nathan; Morgan, Philip B; Helland, Magne; Itoi, Motozumi; Jones, Deborah; Nichols, Jason J; van der Worp, Eef; Woods, Craig A

2010-10-01

Daily disposable contact lenses were introduced into the market 16 years ago. Data that we have gathered from annual contact lens fitting surveys conducted in Australia, Canada, Japan, The Netherlands, Norway, the UK and the USA between 2000 and 2008 indicates an overall increase in daily disposable lens fitting during this period. Daily disposable lenses are especially popular in Japan, Norway and the UK. There is a trend for these lenses to be fitted on a part-time basis. Males are over-represented in daily disposable lens fitting-a trend that is especially evident in Canada. Daily disposable lens wearers are about two years younger than wearers of reusable lenses in Japan and The Netherlands. The convenience and health benefits of daily disposable lenses are expected to fuel continued growth in this sector. Copyright (c) 2010 British Contact Lens Association. Published by Elsevier Ltd. All rights reserved.

Waste Disposal: Long-term Performance Studies for Radioactive Waste Disposal and Hydrogeological Modelling

Energy Technology Data Exchange (ETDEWEB)

Marivoet, J

2000-07-01

The main objectives of SCK-CEN's R and D programme on long-term performance studies are: (1) to develop a methodology and associated tools for assessing the long-term safety of geological disposal of all types of radioactive waste in clay formations and of the shallow-land burial of low-level waste; (2) to assess the performance and to identify the most influential elements of integrated repository systems for the disposal of radioactive waste; (3) to collect geological, piezometric and hydraulic data required for studying the hydrogeological system in north-eastern Belgium; (4) to develop a regional aquifer model for north-easter Belgium and to apply it in the performance assessments for the Mol site; (5) to test, verify and improve computer codes used in the performance assessment calculations of waste disposal concepts and contaminated sites (the computer codes simulate water flow and transport of radionuclides in engineered barriers, aquifers and contaminated sites). The scientific programme and achievements in 1999 are described.

Determining how much mixed waste will require disposal

International Nuclear Information System (INIS)

Kirner, N.P.

1990-01-01

Estimating needed mixed-waste disposal capacity to 1995 and beyond is an essential element in the safe management of low-level radioactive waste disposal capacity. Information on the types and quantities of mixed waste generated is needed by industry to allow development of treatment facilities and by states and others responsible for disposal and storage of this type of low-level radioactive waste. The design of a mixed waste disposal facility hinges on a detailed assessment of the types and quantities of mixed waste that will ultimately require land disposal. Although traditional liquid scintillation counting fluids using toluene and xylene are clearly recognized as mixed waste, characterization of other types of mixed waste has, however, been difficult. Liquid scintillation counting fluids comprise most of the mixed waste generated and this type of mixed waste is generally incinerated under the supplemental fuel provisions of the Resource Conservation and Recovery Act (RCRA) Because there are no Currently operating mixed waste land disposal facilities, it is impossible to make projections of waste requiring land disposal based on a continuation of current waste disposal practices. Evidence indicates the volume of mixed waste requiring land disposal is not large, since generators are apparently storing these wastes. Surveys conducted to date confirm that relatively small volumes of commercially generated mixed waste volume have relied heavily oil generators' knowledge of their wastes. Evidence exists that many generators are confused by the differences between the Atomic Energy Act and the Resource Conservation and Recovery Act (RCRA) on the issue of when a material becomes a waste. In spite of uncertainties, estimates of waste volumes requiring disposal can be made. This paper proposes an eight-step process for such estimates

FUNDING ALTERNATIVES FOR LOW-LEVEL WASTE DISPOSAL

International Nuclear Information System (INIS)

Becker, Bruce D.; Carilli, Jhon

2003-01-01

For 13 years, low-level waste (LLW) generator fees and disposal volumes for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Radioactive Waste Management Sites (RWMSs) had been on a veritable roller coaster ride. As forecast volumes and disposal volumes fluctuated wildly, generator fees were difficult to determine and implement. Fiscal Year (FY) 2000 forecast projections were so low, the very existence of disposal operations at the Nevada Test Site (NTS) were threatened. Providing the DOE Complex with a viable, cost-effective disposal option, while assuring the disposal site a stable source of funding, became the driving force behind the development of the Waste Generator Access Fee at the NTS. On September 26, 2000, NNSA/NV (after seeking input from DOE/Headquarters [HQ]), granted permission to Bechtel Nevada (BN) to implement the Access Fee for FY 2001 as a two-year Pilot Program. In FY 2001 (the first year the Access Fee was implemented), the NTS Disposal Operations experienced a 90 percent increase in waste receipts from the previous year and a 33 percent reduction in disposal fee charged to the waste generators. Waste receipts for FY 2002 were projected to be 63 percent higher than FY 2001 and 15 percent lower in cost. Forecast data for the outyears are just as promising. This paper describes the development, implementation, and ultimate success of this fee strategy

Safe disposal of surplus plutonium

Science.gov (United States)

Gong, W. L.; Naz, S.; Lutze, W.; Busch, R.; Prinja, A.; Stoll, W.

2001-06-01

About 150 tons of weapons grade and weapons usable plutonium (metal, oxide, and in residues) have been declared surplus in the USA and Russia. Both countries plan to convert the metal and oxide into mixed oxide fuel for nuclear power reactors. Russia has not yet decided what to do with the residues. The US will convert residues into a ceramic, which will then be over-poured with highly radioactive borosilicate glass. The radioactive glass is meant to provide a deterrent to recovery of plutonium, as required by a US standard. Here we show a waste form for plutonium residues, zirconia/boron carbide (ZrO 2/B 4C), with an unprecedented combination of properties: a single, radiation-resistant, and chemically durable phase contains the residues; billion-year-old natural analogs are available; and criticality safety is given under all conceivable disposal conditions. ZrO 2/B 4C can be disposed of directly, without further processing, making it attractive to all countries facing the task of plutonium disposal. The US standard for protection against recovery can be met by disposal of the waste form together with used reactor fuel.

Optimized candidal biofilm microtiter assay

NARCIS (Netherlands)

Krom, Bastiaan P.; Cohen, Jesse B.; Feser, Gail E. McElhaney; Cihlar, Ronald L.

Microtiter based candidal biofilm formation is commonly being used. Here we describe the analysis of factors influencing the development of candidal biofilms such as the coating with serum, growth medium and pH. The data reported here show that optimal candidal biofilm formation is obtained when

Psychological impact of colostomy pouch change and disposal.

Science.gov (United States)

McKenzie, Frances; White, Craig A; Kendall, Sally; Finlayson, Aileen; Urquhart, Mary; Williams, Isabel

This article presents some of the findings from a multicentre cross-sectional correlational study to evaluate the relationship between colostomy pouch change and disposal practices and the patient's psychological wellbeing. Five questionnaires were used in a one-off interview with 86 patients. Patients were assessed at between one and four months postoperatively. Results from the Pouch Change and Disposal questionnaire showed that only 25% of patients found disposal of used appliances the most difficult part of their pouch change and disposal routine. Half felt that their body was out of their control and 33% reported avoiding social and leisure activities due to what was involved in their pouch change and disposal routine. Patients cited several factors, such as minimizing odour and having an appliance that could flush away, as factors which would help them to stop avoiding these activities. Stoma care nurses have a unique opportunity to improve the psychological wellbeing of their patients by considering the aspects of pouch change and disposal that pose the greatest challenge to individuals. Use of a modified version of the Pouch Change and Disposal questionnaire may be a useful tool in identifying those at risk of impaired quality of life.

Geological disposal: security and R and D. Security of 'second draft for R and D of geological disposal'

International Nuclear Information System (INIS)

Shiotsuki, Masao; Miyahara, Kaname

2003-01-01

The second draft for R and D of geological disposal (second draft) was arranged in 1999. The idea of security of geological disposal in the second draft is explained. The evaluation results of the uncertainty analysis and an example of evaluation of the effect of separation nuclear transmutation on the geological disposal are shown. The construction of strong engineered barrier is a basic idea of geological disposal system. Three processes such as isolation, engineering countermeasures and safety evaluation are carried out for the security of geological disposal. The security of geological environment for a long time of 12 sites in Japan was studied by data. Provability of production and enforcement of engineered barrier were confirmed by trial of over pack, tests and the present and future technologies developed. By using the conditions of reference case in the second draft, the evaluation results of dose effects in the two cases: 1) 90 to 99% Cs and Sr removed from HLW (High Level radioactive Waste) and 2) high stripping ratio of actinium series are explained. (S.Y.)

Crushing leads to waste disposal savings for FUSRAP

Energy Technology Data Exchange (ETDEWEB)

Darby, J. [Department of Energy, Oak Ridge, TN (United States)

1997-02-01

In this article the author discusses the application of a rock crusher as a means of implementing cost savings in the remediation of FUSRAP sites. Transportation and offsite disposal costs are at present the biggest cost items in the remediation of FUSRAP sites. If these debris disposal problems can be handled in different manners, then remediation savings are available. Crushing can result in the ability to handle some wastes as soil disposal problems, which have different disposal regulations, thereby permitting cost savings.

A Comparison of Distillery Stillage Disposal Methods

OpenAIRE

V. Sajbrt; M. Rosol; P. Ditl

2010-01-01

This paper compares the main stillage disposal methods from the point of view of technology, economics and energetics. Attention is paid to the disposal of both solid and liquid phase. Specifically, the following methods are considered: a) livestock feeding, b) combustion of granulated stillages, c) fertilizer production, d) anaerobic digestion with biogas production and e) chemical pretreatment and subsequent secondary treatment. Other disposal techniques mentioned in the literature (electro...

Radioactive waste disposal: an international law perspective

International Nuclear Information System (INIS)

Barrie, G.N.

1989-01-01

The question of radioactive waste disposal is the most intractable technical and political problem facing nuclear industry. Environmentalists world-wide demand a nuclear waste policy that must be ecologically acceptable internationally. Radioactive wastes and oil pollution were the first two types of marine pollution to receive international attention and various marine pollution controls were established. Ocean disposal was co-ordinated by the Nuclear Energy Agency and the Organization of Economic Co-operation and Development in 1967. The first treaty was the 1958 Convention on the High Seas (High Seas Convention). In response to its call for national co-operation the International Atomic Energy Agency (IAEA) established its Brynielson panel. The IAEA first issued guidelines on sea dumping in 1961. The London Dumping Convention, written in 1972, is the only global agreement concerned solely with the disposal of wastes in the marine environment by dumping. None of the global agreements make specific reference to sea-bed disposal of high-level radioactive wastes. Negotiations began at the Third UN Conference on the Law of the Sea (UNCLOS III) for the codification of a comprehensive treaty concerned with the protection, conservation, sustainable use and development of the marine environment. Burial in deep geological formations is a method of HLW disposal which decreases the chances of accidental intrusion by mankind and has little likelihood of malicious intrusion. National waste management programmes of different countries differ but there is agreement on the acceptable technical solutions to issues of waste management. The final disposition of HLW - storage or disposal - has not been decisively determined, but there is growing consensus that geological land-based disposal is the most viable alternative. Expanded international technical co-operation could well reduce the time needed to develop effective waste disposal mechanisms

Community syringe collection and disposal policies in 16 states.

Science.gov (United States)

Turnberg, Wayne L; Jones, T Stephen

2002-01-01

To review laws, regulations, and guidelines that affect the collection and disposal of hypodermic needles, syringes, and lancets used outside of professional health care settings (hereafter referred to as "community syringes"). Law and policy analysis. Alabama, California, Florida, Georgia, Hawaii, Massachusetts, Michigan, Minnesota, New Jersey, New York, Ohio, Oregon, Rhode Island, South Carolina, Washington, and Wisconsin. Information on syringe collection and disposal in the community was gathered from federal and state records and state agency personnel. Legally permissible means of syringe collection and disposal available to persons in the community injecting medical treatments and injection drug users. Laws, regulations, or guidelines in 13 states allowed community syringes to be legally discarded in household trash; guidelines for in-trash disposal varied among the states. Only 6 states had laws or regulations that specifically addressed community syringe collection. In 10 states, infectious waste laws and regulations that apply to medical facilities such as clinics would also apply to community syringe collection sites. In the 16 states studied, laws, regulations, and guidelines relating to community syringe collection and disposal were somewhat inconsistent and confusing and presented potential barriers to safe disposal. States should consider amending laws, regulations, and guidelines to promote community syringe collection programs. A national effort is needed to achieve consistent community syringe collection and disposal laws and guidelines for all states. Pharmacists can aid in safe syringe disposal by counseling their patients about safe disposal, providing or selling sharps containers, and accepting used syringes for safe disposal. Pharmacists can join other interested groups in advocating clarification of disposal laws and regulations that favor community programs designed to keep syringes out of the trash so that they can be disposed of as

Waste disposal into the sea

International Nuclear Information System (INIS)

Ehlers, P.; Kunig, P.

1987-01-01

The waste disposal at sea is regulated for the most part by national administrative law, which mainly is based on international law rules supplemented by EC-law. The dumping of low-level radioactive waste into the sea is more and more called into question. The disposal of high-level radioactive waste into the subsoil of the sea does not correspond to the London Convention. (WG) [de

Disposability Assessment: Aluminum-Based Spent Nuclear Fuel Forms

Energy Technology Data Exchange (ETDEWEB)

Vinson, D.W.

1998-11-06

This report provides a technical assessment of the Melt-Dilute and Direct Al-SNF forms in disposable canisters with respect to meeting the requirements for disposal in the Mined Geologic Disposal System (MGDS) and for interim dry storage in the Treatment and Storage Facility (TSF) at SRS.

Shallow ground disposal of radioactive wastes. A guidebook

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

This guidebook outlines the factors to be considered in site selection, design, operation, shut-down and surveillance as well as the regulatory requirements of repositories for safe disposal of radioactive waste in shallow ground. No attempt is made to summarize the existing voluminous literature on the many facets of radioactive waste disposal. In the context of this guidebook, shallow ground disposal refers to the emplacement of radioactive waste, with or without engineered barriers, above or below the ground surface, where the final protective covering is of the order of a few metres thick. Deep geological disposal and other underground disposal methods, management of mill tailings and disposal into the sea have been or will be considered in other IAEA publications. These guidelines have been made sufficiently general to cover a broad variety of climatic, hydrogeological and biological conditions. They may need to be interpreted or modified to reflect local conditions and national regulations.

Nuclear fuel waste disposal in Canada

International Nuclear Information System (INIS)

Dormuth, K.W.; Gillespie, P.A.

1990-05-01

Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

Nuclear fuel waste disposal in Canada

International Nuclear Information System (INIS)

Dormuth, K.W.; Gillespie, P.A.

1990-05-01

Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under the Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

Shallow land disposal, the french system

International Nuclear Information System (INIS)

Barthoux, A.; Marque, Y.

1986-01-01

Since 1969, low and medium activity waste are disposed of in France at the Centre Manche. The management system set up covers the whole of the operations, from the sorting of the wastes and their conditioning to the final disposal. Safety standards and technical issues were found satisfactory by the National Safety Authority and they are the basis of the program for the realization of two new disposal sites which should take over from the Centre Manche loaded towards 1990. ANDRA, a National Agency, is responsible for the long term management of radioactive waste, in France [fr

From non-disposable to disposable, treatment of pyrophoric or gas forming waste forms for disposal - Thermal treatment of pyrophoric or gas-forming metals

International Nuclear Information System (INIS)

Oesterberg, Carl; Lindberg, Maria

2014-01-01

In order to dispose of waste in either a deep geological disposal or in a shallower repository there are several demands that the waste and its package must fulfil, one is that it is not to react with oxygen or the waste package or backfill in the repository, i.e. concrete or grout. The waste forms that do not fulfil this particular criterion must be treated in some way to render the waste non-reactive. One of these waste are metallic uranium. Metallic uranium is not only an issue originating from the nuclear industry, as old types of fuel, it is also present in, for example, transport flasks and as samples used in schools, which all has to be disposed of sooner or later. Another waste that arise is magnesium doped with thorium, originating from the aviation, aerospace and missile industry. These alloys are now being replaced with others without thorium so they are in need of handling and possibly treatment before disposal. Magnesium metal is also pyrophoric, in particular in molten or powder form. In order to evaluate thermally treating these metals in a very controlled environment, such as a pyrolysis vessel, experimental work has been performed. The aim of the thermal treatment is to oxidise the metals and obtain an oxide with low leachability. Inactive trials were performed, first using small amount of magnesium tape followed by using Cerium instead of uranium, to check the ability of controlling the process. After the process had been deemed safe the next step was to test the process first with metallic uranium and thereafter with magnesium thorium alloy. The first results show that the oxidation process can be totally controlled and safe. The results show that the metals are oxidised and no longer reactive and can in principle be disposed of. The test will continue and further results will be reported. (authors)

Detailed description of a new management system for solid, short-lived low and intermediate level radioactive waste at Ignalina NPP

International Nuclear Information System (INIS)

2002-01-01

The objective is to modify and extend the existing system at the Ignalina Nuclear Power Plant (INPP) for handling of Very Low Level Waste (VLLW), short lived Low and Intermediate Level Waste (LLW-SL and ILW-SL). The ultimate aim is to reduce the risks and the influence on the personnel and the environment. According to the request from INPP, the modified system is based on the existence of an incineration plant. This system description describes treatment of non-combustible VLLW, LLW-SL and ILW-SL at a new waste handling facility (WHF) located in the future buildings 159/2 and 159/3 at the INPP. The new WHF is also handling Exempt Waste (EW), Reusable Material (RM) and Free Release Goods (FRG). The buildings 159/2 and 159/3 are future extensions of the existing building 159. (author)

20 CFR 209.16 - Disposal of payroll records.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 1 2010-04-01 2010-04-01 false Disposal of payroll records. 209.16 Section... RAILROAD EMPLOYERS' REPORTS AND RESPONSIBILITIES § 209.16 Disposal of payroll records. Employers may dispose of payroll records for periods subsequent to 1936, provided that the payroll records are more than...

12 CFR 571.83 - Disposal of consumer information.

Science.gov (United States)

2010-01-01

... REPORTING Duties of Users of Consumer Reports Regarding Address Discrepancies and Records Disposal § 571.83 Disposal of consumer information. (a) Scope. This section applies to savings associations whose deposits... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Disposal of consumer information. 571.83...

12 CFR 334.83 - Disposal of consumer information.

Science.gov (United States)

2010-01-01

... GENERAL POLICY FAIR CREDIT REPORTING Duties of Users of Consumer Reports Regarding Address Discrepancies and Records Disposal § 334.83 Disposal of consumer information. (a) In general. You must properly... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Disposal of consumer information. 334.83...

12 CFR 615.5143 - Disposal of ineligible investments.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Disposal of ineligible investments. 615.5143... AFFAIRS, LOAN POLICIES AND OPERATIONS, AND FUNDING OPERATIONS Investment Management § 615.5143 Disposal of ineligible investments. You must dispose of an ineligible investment within 6 months unless we approve, in...

Crystalline and Crystalline International Disposal Activities

Energy Technology Data Exchange (ETDEWEB)

Viswanathan, Hari S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reimus, Paul William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Makedonska, Nataliia [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hyman, Jeffrey De' Haven [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karra, Satish [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dittrich, Timothy M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-21

This report presents the results of work conducted between September 2014 and July 2015 at Los Alamos National Laboratory in the crystalline disposal and crystalline international disposal work packages of the Used Fuel Disposition Campaign (UFDC) for DOE-NE’s Fuel Cycle Research and Development program.

Preliminary research on groundwater flow characteristics of the low- and Intermediate-level radioactive waste disposal site

International Nuclear Information System (INIS)

Koh, Young Kwon; Bae, Dae Seok; Kim, Geon Young; Ryu, Ji Hoon; Park, Kyung Woo; Ji, Sung Hoon; Kim, Kyung Su

2009-08-01

Preliminary site survey and candidate survey complements the purpose of the current site selection and disposal place selected for the study because of hydraulic to the geological survey done for the general idea was brought in the field of geochemistry survey was made. Therefore, this report hydraulic - the underlying structure of the model deterministic deformation zone model to focus on the configuration kept, according to data survey by hydraulic and hydraulic rock star pitcher trying to figure out the scope of the structure factors were hydraulic. Groundwater and related land place shares characteristics of the existing data and complementary research and laboratory research performed on the basis of geochemical data, based on the following major finding were present

2005 dossier: granite. Tome: phenomenological evolution of the geologic disposal

International Nuclear Information System (INIS)

2005-01-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the phenomenological aspects of the geologic disposal of high-level and long-lived radioactive wastes (HLLL) in granite formations. Content: 1 - introduction: ANDRA's research program on disposal in granitic formation; 2 - the granitic environment: geologic history, French granites; 3 - HLLL wastes and disposal design concepts; 4 - identification, characterization and modeling of a granitic site: approach, geologic modeling, hydrologic and hydro-geochemical modeling, geomechanical and thermal modeling, long-term geologic evolution of a site; 5 - phenomenological evolution of a disposal: main aspects of the evolution of a repository with time, disposal infrastructures, B-type wastes disposal area, C-type wastes disposal area; spent fuels disposal area, radionuclides transfer and retention in the granitic environment; 6 - conclusions: available knowledge, methods and tools for the understanding and modeling of the phenomenological evolution of a granitic disposal site. (J.S.)

The Dutch geologic radioactive waste disposal project

International Nuclear Information System (INIS)

Hamstra, J.; Verkerk, B.

1981-01-01

The Final Report reviews the work on geologic disposal of radioactive waste performed in the Netherlands over the period 1 January 1978 to 31 December 1979. The attached four topical reports cover detailed subjects of this work. The radionuclide release consequences of an accidental flooding of the underground excavations during the operational period was studied by the institute for Atomic Sciences in Agriculture (Italy). The results of the quantitative examples made for different effective cross-sections of the permeable layer connecting the mine excavations with the boundary of the salt dome, are that under all circumstances the concentration of the waste nuclides in drinking water will remain well within the ICRP maximum permissible concentrations. Further analysis work was done on what minima can be achieved for both the maximum local rock salt temperatures at the disposal borehole walls and the maximum global rock salt temperatures halfway between a square of disposal boreholes. Different multi-layer disposal configurations were analysed and compared. A more detailed description is given of specific design and construction details of a waste repository such as the shaft sinking and construction, the disposal mine development, the mine ventilation and the different plugging and sealing procedures for both the disposal boreholes and the shafts. Thanks to the hospitality of the Gesellschaft fuer Strahlenforschung, an underground working area in the Asse mine became available for performing a dry drilling experiment, which resulted successfully in the drilling of a 300 m deep disposal borehole from a mine room at the -750 m level

12 CFR 41.83 - Disposal of consumer information.

Science.gov (United States)

2010-01-01

... Duties of Users of Consumer Reports Regarding Address Discrepancies and Records Disposal § 41.83 Disposal of consumer information. (a) Definitions as used in this section. (1) Bank means national banks... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Disposal of consumer information. 41.83 Section...

Disposal of high level radioactive wastes in geological formations

International Nuclear Information System (INIS)

Martins, L.A.M.; Carvalho Bastos, J.P. de

1978-01-01

The disposal of high-activity radioactive wastes is the most serious problem for the nuclear industry. Among the solutions, the disposal of wastes in approriated geological formations is the most realistic and feasible. In this work the methods used for geological disposal, as well as, the criteria, programs and analysis for selecting a bite for waste disposal are presented [pt

Issue-Advocacy versus Candidate Advertising: Effects on Candidate Preferences and Democratic Process.

Science.gov (United States)

Pfau, Michael; Holbert, R. Lance; Szabo, Erin Alison; Kaminski, Kelly

2002-01-01

Examines the influence of soft-money-sponsored issue-advocacy advertising in U.S. House and Senate campaigns, comparing its effects against candidate-sponsored positive advertising and contrast advertising on viewers' candidate preferences and on their attitude that reflect democratic values. Reveals no main effects for advertising approach on…

Borehole disposal of spent radiation sources: 1. Principles

International Nuclear Information System (INIS)

Blerk, J.J. van; Kozak, M.W.

2000-01-01

Large numbers of spent radiation sources from the medical and other technical professions exist in many countries, even countries that do not possess facilities related to the nuclear fuel cycle, that have to be disposed. This is particularly the case in Africa, South America and some members of the Russian Federation. Since these sources need to be handled separately from the other types of radioactive waste, mainly because of their activity to volume ratio, countries (even those with access to operational repositories) find it difficult to manage and dispose this waste. This has led to the use of boreholes as disposal units for these spent sources by some members of the Russian Federation and in South Africa. However, the relatively shallow boreholes used by these countries are not suitable for the disposal of isotopes with long half-lifes, such as 226 Ra and 241 Am. With this in mind the Atomic Energy Corporation of South Africa initiated the development of the BOSS disposal concept - an acronym for Borehole disposal Of Spent Sources - as part of an International Atomic Energy Agency (IAEA) AFRA I-14 Technical Corporation (TC) project. In this paper, the principles of this disposal concept, which is still under development, will be discussed. (author)

Economics of low-level radioactive waste disposal

International Nuclear Information System (INIS)

Schafer, J.; Jennrich, E.

1983-01-01

Regardless of who develops new low-level radioactive waste disposal sites or when, economics will play a role. To assist in this area the Department of Energy's Low-Level Radioactive Waste Management Program has developed a computer program, LLWECON, and data base for projecting disposal site costs. This program and its non-site specific data base can currently be used to compare the costs associated with various disposal site development, financing, and operating scenarios. As site specific costs and requirements are refined LLWECON will be able to calculate exact life cycle costs for each facility. While designed around shallow land burial, as practiced today, LLWECON is flexible and the input parameters discrete enough to be applicable to other disposal options. What the program can do is illustrated

Concept development for HLW disposal research tunnel

International Nuclear Information System (INIS)

Queon, S. K.; Kim, K. S.; Park, J. H.; Jeo, W. J.; Han, P. S.

2003-01-01

In order to dispose high-level radioactive waste in a geological formation, it is necessary to assess the safety of a disposal concept by excavating a research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, analysis of the characteristics of the disposal research tunnel, which is planned to be constructed at KAERI site, calculation of the influence of basting impact on neighbor facilities, and computer simuation for mechanical stability analysis using a three-dimensional code, FLAC3D, had been carried out to develop the design concept of the research tunnel

UK surplus source disposal programme - 16097

International Nuclear Information System (INIS)

John, Gordon H.; Reeves, Nigel; Nisbet, Amy C.; Garnett, Andrew; Williams, Clive R.

2009-01-01

The UK Surplus Source Disposal Programme (SSDP), managed by the Environment Agency, was designed to remove redundant radioactive sources from the public domain. The UK Government Department for Environment, Food and Rural Affairs (Defra) was concerned that disused sources were being retained by hospitals, universities and businesses, posing a risk to public health and the environment. AMEC provided a range of technical and administrative services to support the SSDP. A questionnaire was issued to registered source holders and the submitted returns compiled to assess the scale of the project. A member of AMEC staff was seconded to the Environment Agency to provide technical support and liaise directly with source holders during funding applications, which would cover disposal costs. Funding for disposal of different sources was partially based on a sliding scale of risk as determined by the IAEA hazard categorisation system. This funding was also sector dependent. The SSDP was subsequently expanded to include the disposal of luminised aircraft instruments from aviation museums across the UK. These museums often hold significant radiological inventories, with many items being unused and in a poor state of repair. These instruments were fully characterised on site by assessing surface dose rate, dimensions, source integrity and potential contamination issues. Calculations using the Microshield computer code allowed gamma radiation measurements to be converted into total activity estimates for each source. More than 11,000 sources were disposed of under the programme from across the medical, industrial, museum and academic sectors. The total activity disposed of was more than 8.5 E+14 Bq, and the project was delivered under budget. (authors)

The surface disposal concept for LIL/SL waste

International Nuclear Information System (INIS)

2011-01-01

Most low-level and intermediate-level short-lived (LIL/SL) waste result from the nuclear-power industry. Their specific activity level is sufficiently high to justify a protective conditioning and to ensure proper confinement until that level has decreased to harmless levels for human beings and the environment (a few centuries considering the half lives of the radionuclides contained in LIL/SL waste). The disposal concept for such residues relies on a multi-barrier protective system, each barrier being designed to fulfil different or redundant functions in order to delay or mitigate radionuclide transfers first into the environment and onwards to human beings. The originality of the concept pertains to its flexibility, since: it is adaptable to various geological environments and its overall performance may be guaranteed by modulating that of the engineered barriers, and it is suitable for the disposal of different types and sizes of waste packages, as long as their characteristics are consistent with acceptance criteria, which are de facto specific to each case. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects. The safety of the disposal facility is guaranteed by the combination of the package, the concrete structures, the filling materials between packages and the watertight clay cap that will be installed at the end of the operating lifetime of the facility. That layout also takes all natural risks into account. Lastly, all disposal structures are built away from any potential flood zones and from the highest possible level of the groundwater table. Concrete and metal packages are disposed of in slightly different structures. Once a structure is full, concrete packages are immobilised with gravel, whereas metal packages are blocked in place by pouring concrete between them. Once a disposal structure is

The surface disposal concept for LIL/SL waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

Most low-level and intermediate-level short-lived (LIL/SL) waste result from the nuclear-power industry. Their specific activity level is sufficiently high to justify a protective conditioning and to ensure proper confinement until that level has decreased to harmless levels for human beings and the environment (a few centuries considering the half lives of the radionuclides contained in LIL/SL waste). The disposal concept for such residues relies on a multi-barrier protective system, each barrier being designed to fulfil different or redundant functions in order to delay or mitigate radionuclide transfers first into the environment and onwards to human beings. The originality of the concept pertains to its flexibility, since: it is adaptable to various geological environments and its overall performance may be guaranteed by modulating that of the engineered barriers, and it is suitable for the disposal of different types and sizes of waste packages, as long as their characteristics are consistent with acceptance criteria, which are de facto specific to each case. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects. The safety of the disposal facility is guaranteed by the combination of the package, the concrete structures, the filling materials between packages and the watertight clay cap that will be installed at the end of the operating lifetime of the facility. That layout also takes all natural risks into account. Lastly, all disposal structures are built away from any potential flood zones and from the highest possible level of the groundwater table. Concrete and metal packages are disposed of in slightly different structures. Once a structure is full, concrete packages are immobilised with gravel, whereas metal packages are blocked in place by pouring concrete between them. Once a disposal structure is

Advances in Geologic Disposal System Modeling and Shale Reference Cases

Energy Technology Data Exchange (ETDEWEB)

Mariner, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-22

The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (OFCT) is conducting research and development (R&D) on geologic disposal of spent nuclear fuel (SNF) and high level nuclear waste (HLW). Two high priorities for SFWST disposal R&D are design concept development and disposal system modeling (DOE 2011, Table 6). These priorities are directly addressed in the SFWST Generic Disposal Systems Analysis (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media (e.g., salt, granite, shale, and deep borehole disposal).

Whither nuclear waste disposal?

Energy Technology Data Exchange (ETDEWEB)

Cotton, T A [JK Research Associates, Silver Spring, MD (United States)

1990-07-01

With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site.

Whither nuclear waste disposal?

International Nuclear Information System (INIS)

Cotton, T.A.

1990-01-01

With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

Final disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Anon,

1995-10-01

The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

Final disposal of nuclear waste

International Nuclear Information System (INIS)

Anon.

1995-01-01

The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

Cost considerations in remediation and disposal

International Nuclear Information System (INIS)

Dance, J.T.; Huddleston, R.D.

1999-01-01

Opportunities for assessing the costs associated with the reclamation and remediation of sites contaminated by oilfield wastes are discussed. The savings can be maximized by paying close attention to five different aspects of the overall site remediation and disposal process. These are: (1) highly focused site assessment, (2) cost control of treatment and disposal options, (3) value added cost benefits, (4) opportunities to control outside influences during the remedial process, and (5) opportunities for managing long-term liabilities and residual risk remaining after the remedial program is completed. It is claimed that addressing these aspects of the process will ultimately lower the overall cost of site remediation and waste disposal

Radioactive waste management and disposal in Australia

International Nuclear Information System (INIS)

Harries, J.R.

1997-01-01

A national near-surface repository at a remote and arid location is proposed for the disposal of solid low-level and short-lived intermediate-level radioactive wastes in Australia. The repository will be designed to isolate the radioactive waste from the human environment under controlled conditions and for a period long enough for the radioactivity to decay to low levels. Compared to countries that have nuclear power programs, the amount of waste in Australia is relatively small. Nevertheless, the need for a national disposal facility for solid low-level radioactive and short-lived intermediate-level radioactive wastes is widely recognised and the Federal Government is in the process of selecting a site for a national near-surface disposal facility for low and short-lived intermediate level wastes. Some near surface disposal facilities already exist in Australia, including tailings dams at uranium mines and the Mt Walton East Intractable Waste Disposal Facility in Western Australia which includes a near surface repository for low level wastes originating in Western Australia. 7 refs, 1 fig., 2 tabs

Method of ground disposal of radioactive waste

International Nuclear Information System (INIS)

Harashina, Heihachi.

1991-01-01

Rock bases are drilled to form a disposal hole, an overhanging hole and a burying hole each as a shaft. An appropriate number of canisters prepared by vitrification of high level radioactive wastes are charged in the disposal hole with a gap to the inner wall of the hole. Shock absorbers each made of bentonite are filled between each of the canisters and between the canister and the inner wall of the disposal hole, and the canisters are entirely covered with the layer of the shock absorbers. Further, plucking materials having water sealing property such as cement mortar are filled thereover. With such a constitution, in a case if water should intrude into the overhung portion, since the disposal hole is covered with the large flange portion in addition to the water sealing performance of the plucking, the shock absorbers and the canisters undergo no undesirable effects. Further, in a case if water should intrude to the disposal hole, the shock absorber layers are swollen by water absorption, to suppress the intrusion of water. (T.M.)

Important issues in disposal of L/ILW

International Nuclear Information System (INIS)

McCombie, C.

1987-01-01

Today waste disposal is a challenging technical and political issue. In many countries the acceptance of nuclear power has been tied formally or informally to the convincing demonstration that we can dispose of all radioactive wastes with a very high degree of safety exceeding the expected for other toxic or hazardous wastes. The importance of the public acceptance aspects and the more obviously striking characteristics of high-level wastes (HLW) - in particular their high initial radiation, their heat emission and their long decay times - led to an early concentration of effort on planning and analyzing HLW disposal. On the other hand, the problems of disposing of low- and inter-mediate-level wastes (L/ILW) are in many ways more immediate. These wastes are arising today in quantities which can make continued storge troublesome; accordingly increased effort is being expended in many countries on organizing the safe, final disposal of L/ILW. Some of the technical issues of importance which arise in the corresponding planning and analysis of repository projects for L/ILW are discussed in this paper

Integrated Disposal Facility

Data.gov (United States)

Federal Laboratory Consortium — Located near the center of the 586-square-mile Hanford Site is the Integrated Disposal Facility, also known as the IDF.This facility is a landfill similar in concept...

Geotechnical engineering for ocean waste disposal. An introduction

Science.gov (United States)

Lee, Homa J.; Demars, Kenneth R.; Chaney, Ronald C.; ,

1990-01-01

As members of multidisciplinary teams, geotechnical engineers apply quantitative knowledge about the behavior of earth materials toward designing systems for disposing of wastes in the oceans and monitoring waste disposal sites. In dredge material disposal, geotechnical engineers assist in selecting disposal equipment, predict stable characteristics of dredge mounds, design mound caps, and predict erodibility of the material. In canister disposal, geotechnical engineers assist in specifying canister configurations, predict penetration depths into the seafloor, and predict and monitor canister performance following emplacement. With sewage outfalls, geotechnical engineers design foundation and anchor elements, estimate scour potential around the outfalls, and determine the stability of deposits made up of discharged material. With landfills, geotechnical engineers evaluate the stability and erodibility of margins and estimate settlement and cracking of the landfill mass. Geotechnical engineers also consider the influence that pollutants have on the engineering behavior of marine sediment and the extent to which changes in behavior affect the performance of structures founded on the sediment. In each of these roles, careful application of geotechnical engineering principles can contribute toward more efficient and environmentally safe waste disposal operations.

Household waste disposal in Mekelle city, Northern Ethiopia

International Nuclear Information System (INIS)

Tadesse, Tewodros; Ruijs, Arjan; Hagos, Fitsum

2008-01-01

In many cities of developing countries, such as Mekelle (Ethiopia), waste management is poor and solid wastes are dumped along roadsides and into open areas, endangering health and attracting vermin. The effects of demographic factors, economic and social status, waste and environmental attributes on household solid waste disposal are investigated using data from household survey. Household level data are then analyzed using multinomial logit estimation to determine the factors that affect household waste disposal decision making. Results show that demographic features such as age, education and household size have an insignificant impact over the choice of alternative waste disposal means, whereas the supply of waste facilities significantly affects waste disposal choice. Inadequate supply of waste containers and longer distance to these containers increase the probability of waste dumping in open areas and roadsides relative to the use of communal containers. Higher household income decreases the probability of using open areas and roadsides as waste destinations relative to communal containers. Measures to make the process of waste disposal less costly and ensuring well functioning institutional waste management would improve proper waste disposal

Disposal of hazardous wastes

International Nuclear Information System (INIS)

Barnhart, B.J.

1978-01-01

The Fifth Life Sciences Symposium entitled Hazardous Solid Wastes and Their Disposal on October 12 through 14, 1977 was summarized. The topic was the passage of the National Resources Conservation and Recovery Act of 1976 will force some type of action on all hazardous solid wastes. Some major points covered were: the formulation of a definition of a hazardous solid waste, assessment of long-term risk, list of specific materials or general criteria to specify the wastes of concern, Bioethics, sources of hazardous waste, industrial and agricultural wastes, coal wastes, radioactive wastes, and disposal of wastes

Disposal of Radioactive Waste. Specific Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Requirements publication applies to the disposal of radioactive waste of all types by means of emplacement in designed disposal facilities, subject to the necessary limitations and controls being placed on the disposal of the waste and on the development, operation and closure of facilities. The classification of radioactive waste is discussed. This Safety Requirements publication establishes requirements to provide assurance of the radiation safety of the disposal of radioactive waste, in the operation of a disposal facility and especially after its closure. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. This is achieved by setting requirements on the site selection and evaluation and design of a disposal facility, and on its construction, operation and closure, including organizational and regulatory requirements.

Subseabed Disposal Program Plan. Volume I. Overview

International Nuclear Information System (INIS)

1981-07-01

The primary objective of the Subseabed Disposal Program (SDP) is to assess the scientific, environmental, and engineering feasibility of disposing of processed and packaged high-level nuclear waste in geologic formations beneath the world's oceans. High-level waste (HLW) is considered the most difficult of radioactive wastes to dispose of in oceanic geologic formations because of its heat and radiation output. From a scientific standpoint, the understanding developed for the disposal of such HLW can be used for other nuclear wastes (e.g., transuranic - TRU - or low-level) and materials from decommissioned facilities, since any set of barriers competent to contain the heat and radiation outputs of high-level waste will also contain such outputs from low-level waste. If subseabed disposal is found to be feasible for HLW, then other factors such as cost will become more important in considering subseabed emplacement for other nuclear wastes. A secondary objective of the SDP is to develop and maintain a capability to assess and cooperate with the seabed nuclear waste disposal programs of other nations. There are, of course, a number of nations with nuclear programs, and not all of these nations have convenient access to land-based repositories for nuclear waste. Many are attempting to develop legislative and scientific programs that will avoid potential hazards to man, threats to other ocean uses, and marine pollution, and they work together to such purpose in meetings of the international NEA/Seabed Working Group. The US SDP, as the first and most highly developed R and D program in the area, strongly influences the development of subseabed-disposal-related policy in such nations

Estimating waste disposal quantities from raw waste samples

International Nuclear Information System (INIS)

Negin, C.A.; Urland, C.S.; Hitz, C.G.; GPU Nuclear Corp., Middletown, PA)

1985-01-01

Estimating the disposal quantity of waste resulting from stabilization of radioactive sludge is complex because of the many factors relating to sample analysis results, radioactive decay, allowable disposal concentrations, and options for disposal containers. To facilitate this estimation, a microcomputer spread sheet template was created. The spread sheet has saved considerable engineering hours. 1 fig., 3 tabs

Pathways for Disposal of Commercially-Generated Tritiated Waste

Energy Technology Data Exchange (ETDEWEB)

Halverson, Nancy V. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Environmental Sciences and Biotechnology

2016-09-26

From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste

Pathways for Disposal of Commercially-Generated Tritiated Waste

International Nuclear Information System (INIS)

Halverson, Nancy V.

2016-01-01

From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste

Disposal leachates treatment

Energy Technology Data Exchange (ETDEWEB)

Coulomb, I.; Renaud, P. (SITA, 75 - Paris (France)); Courant, P. (FD Conseil, 78 - Gargenville (France)); Manem, J.; Mandra, V.; Trouve, E. (Lyonnaise des Eaux-Dumez, 78 - Le Pecq (France))

1993-12-01

Disposal leachates are complex and variable effluents. The use of a bioreactor with membranes, coupled with a reverse osmosis unit, gives a new solution to the technical burying centers. Two examples are explained here.

Management and disposal of radioactive waste from clean-up operations

International Nuclear Information System (INIS)

Lehto, J.

1997-01-01

Clean-up of large contaminated areas may create enormous amounts of radioactive waste which need to be safely disposed of. Disposal of the waste may include pre-treatment and transportation to a final repository. There is much experience of the removal and disposal of large amounts of radioactive contaminated material from uranium mill tailings sites. For example, in Salt Lake City, USA, two million tons of radium-containing waste was transported 140 km by rail to a disposal site. In Port Hope, Canada, 70,000 cubic meters of similar waste were moved by road to a disposal site 350 km away. The disposal of the uranium mill tailings can be pre-planned, but an accident situation is quite different. In an emergency, decisions on how to deal with the waste from the clean-up may have to be made rapidly and disposal options may be limited. After the Chernobyl accident, large amounts of contaminated material (mainly soil and trees) were disposed of in shallow pits and surface mounds. Overall, approximately 4x10 6 m 3 of waste were distributed between about 800 disposal sites. Because the amounts of waste after a major nuclear accident could be large, their final disposal may require large human and capital resources. Depending on the scale it is possible that the wastes will have to be placed in several final disposal sites. These are likely to be pits or surface mounds. Such repositories may need clay or concrete liners to prevent migration of the radionuclides from the disposal sites. (EG)

Salt disposal of heat-generating nuclear waste

International Nuclear Information System (INIS)

Leigh, Christi D.; Hansen, Francis D.

2011-01-01

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United

Salt disposal of heat-generating nuclear waste.

Energy Technology Data Exchange (ETDEWEB)

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from

Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal

Energy Technology Data Exchange (ETDEWEB)

Liu, Hui-Hai; Rutqvist, Jonny; Zheng, Liange; Sonnenthal, Eric; Houseworth, Jim; Birkholzer, Jens

2010-08-31

As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For

Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal

International Nuclear Information System (INIS)

Liu, Hui-Hai; Rutqvist, Jonny; Zheng, Liange; Sonnenthal, Eric; Houseworth, Jim; Birkholzer, Jens

2010-01-01

As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For

Sewage Disposal in Port Harcourt, Nigeria.

Science.gov (United States)

Ayotamuno, M. J.

1993-01-01

This survey of the Port Harcourt, Nigeria, sewage disposal system exemplifies sewage disposal in the developing world. Results reveal that some well-constructed and maintained drains, as well as many open drains and septic tanks, expose women and children to the possibility of direct contact with parasitic organisms and threaten water resources.…

Corrosion behaviour of container materials for geological disposal of high level radioactive waste

International Nuclear Information System (INIS)

Accary, A.

1985-01-01

The disposal of high level radioactive waste in geological formations, based on the multibarrier concept, may include the use of a container as one of the engineered barriers. In this report the requirements imposed on this container and the possible degradation processes are reviewed. Further on an overview is given of the research being carried out by various research centres in the European Community on the assessment of the corrosion behaviour of candidate container materials. The results obtained on a number of materials under various testing conditions are summarized and evaluated. As a result, three promising materials have been selected for a detailed joint testing programme. It concerns two highly corrosion resistant alloys, resp. Ti-Pd (0.2 Pd%) and Hastelloy C4 and one consumable material namely a low carbon steel. Finally the possibilities of modelling the corrosion phenomena are discussed

Long term safety assessment of geological waste disposal systems: issues on release scenarios

International Nuclear Information System (INIS)

Khan, S.A.; Qureshi, A.A.

1995-01-01

Geological insolation of high level nuclear waste is an attractive waste disposal concept. However, long term safety demonstration of this concept is a major challenge to the operators, regulators and the scientific community. Identification of the factors responsible for the release of radionuclides from geosphere to biosphere,is first step in this regard. Current understanding of the release scenarios indicates that faulting, ground after percolation, seismicity, volcanism and human intrusion are the dominating release factors for most of the candidate rock formations. The major source of uncertainties is the probability values of various release events due to random nature of catastrophic geological events and past poor historical records of the frequencies of such events. There is consensus among the experts that the waste release via human intrusion is the most unpredictable scenario at present state of the knowledge. (author)

Public practice regarding disposal of unused medicines in Ireland.

Science.gov (United States)

Vellinga, Akke; Cormican, Sarah; Driscoll, Jacqueline; Furey, Michelle; O'Sullivan, Mai; Cormican, Martin

2014-04-15

Over recent years, a global increase in the use of pharmaceutical products has been observed. EU directives state that "Member states shall ensure that appropriate collection systems are in place for medicinal products that are unused or have expired" (Directive 2001/83/EC and Directive 2004/27/EC). There is no published data on how people in Ireland dispose of unused medicines; therefore the purpose of this study is to establish baseline information on storage and disposal of medicines. Data was collected over two 2-week periods a year apart. People in the streets of Galway and Cork were approached randomly and invited to participate by filling out a questionnaire. The questionnaire was completed by 398 individuals (207 in Galway and 191 in Cork). Unused medicines were kept in the home by 88% of the respondents. The most cited reason for keeping unused medicines was "in case they are needed later" (68%). Of the respondents who had disposed of medicine in the past, 72% had done so inappropriately. Environmentally inappropriate disposal methods were through general waste disposal and via the sewage system. Interestingly, of the people who had received advice on disposal practices from a healthcare professional, 75% disposed of their medicine appropriately. There is little awareness among members of the public regarding appropriate ways to dispose of unused medicines. Our findings suggest that effective communication and established protocols will promote appropriate disposal practices. Copyright © 2014 Elsevier B.V. All rights reserved.

The disposal of low-level radioactive waste into the sea

International Nuclear Information System (INIS)

Saruhashi, Katsuko

1979-01-01

Disposal of low-level radioactive wastes is made both on land and in sea. Though the land disposal has been already carried out in the U.S.A. and the U.S.S.R., it is impossible in the narrow land of Japan. In the United States, the wastes solidified with cement in drums were previously abandoned in deep seas of the Pacific and the Atlantic. This is no longer done presently; instead, the land disposal is employed due to its lower costs. In European countries, the sea disposal is performed under OECDNEA, trial disposal in 1961 and full-scale disposal since 1967, in the Atlantic. Meanwhile, in Japan, test sea disposal will be carried out in the near future in deep sea of the northern Pacific, the important sea area for fisheries. The international trends of the deep sea disposal of low-level wastes and the correspondent trends of the same in Japan, in the past years are described. (J.P.N.)

Application and research of special waste plasma disposal technology

International Nuclear Information System (INIS)

Lan Wei

2007-12-01

The basic concept of plasma and the principle of waste hot plasma disposal technology are simply introduced. Several sides of application and research of solid waste plasma disposal technology are sumed up. Compared to the common technology, the advantages of waste hot plasma disposal technology manifest further. It becomes one of the most prospective and the most attended high tech disposal technology in particular kind of waste disposal field. The article also simply introduces some experiment results in Southwest Institute of Physics and some work on the side of importation, absorption, digestion, development of foreign plasma torch technology and researching new power sources for plasma torch. (authors)

Low level tank waste disposal study

Energy Technology Data Exchange (ETDEWEB)

Mullally, J.A.

1994-09-29

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

Disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Hendee, W.R.

1986-01-01

The generation of low-level radioactive waste is a natural consequence of the societal uses of radioactive materials. These uses include the application of radioactive materials to the diagnosis and treatment of human disease and to research into the causes of human disease and their prevention. Currently, low level radioactive wastes are disposed of in one of three shallow land-burial disposal sites located in Washington, Nevada, and South Carolina. With the passage in December 1980 of Public Law 96-573, The Low-Level Radioactive Waste Policy Act, the disposal of low-level wastes generated in each state was identified as a responsibility of the state. To fulfill this responsibility, states were encouraged to form interstate compacts for radioactive waste disposal. At the present time, only 37 states have entered into compact agreements, in spite of the clause in Public Law 96-573 that established January 1, 1986, as a target date for implementation of state responsibility for radioactive wastes. Recent action by Congress has resulted in postponement of the implementation date to January 1, 1993

The trends of radioactive waste disposal

International Nuclear Information System (INIS)

Nomi, Mitsuhiko

1977-01-01

The disposal of radioactive wastes instead of their treatment has come to be important problem. The future development of nuclear fuel can not be expected unless the final disposal of nuclear fuel cycle is determined. Research and development have been made on the basis of the development project on the treatment of radioactive wastes published by Japan Atomic Energy Commission in 1976. The high level wastes produced by the reprocessing installations for used nuclear fuel are accompanied by strong radioactivity and heat generation. The most promising method for their disposal is to keep them in holes dug at the sea bottom after they are solidified. Middle or low level wastes are divided into two groups; one contains transuranium elements and the other does not. These wastes are preserved on the ground or in shallow strata, while the safe abandonment into the ground or the sea has been discussed about the latter. The co-operations among nations are necessary not only for peaceful utilization of atomic energy but also for radioactive waste disposal. (Kobatake, H.)

Low level tank waste disposal study

International Nuclear Information System (INIS)

Mullally, J.A.

1994-01-01

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site

Evaluations for draft reports on geological disposal

International Nuclear Information System (INIS)

Maekawa, Keisuke; Igarashi, Hiroshi

2002-10-01

This report summarizes the results of the technical evaluations on two reports which are named as 'Overview of the Geological Disposal Facility' and Considerable Factors on Selection of Potential Sites for Geological Disposal' drafted by NUMO (Nuclear Waste Management Organization of Japan). The review of each draft report has been referred to committee (held on 9th September, 2002) and working group (held on 1st October, 2002) which were organized in order to confirm a progress of implementation of geological disposal by government. (author)

Deep borehole disposal of plutonium

International Nuclear Information System (INIS)

Gibb, F. G. F.; Taylor, K. J.; Burakov, B. E.

2008-01-01

Excess plutonium not destined for burning as MOX or in Generation IV reactors is both a long-term waste management problem and a security threat. Immobilisation in mineral and ceramic-based waste forms for interim safe storage and eventual disposal is a widely proposed first step. The safest and most secure form of geological disposal for Pu yet suggested is in very deep boreholes and we propose here that the key to successful combination of these immobilisation and disposal concepts is the encapsulation of the waste form in small cylinders of recrystallized granite. The underlying science is discussed and the results of high pressure and temperature experiments on zircon, depleted UO 2 and Ce-doped cubic zirconia enclosed in granitic melts are presented. The outcomes of these experiments demonstrate the viability of the proposed solution and that Pu could be successfully isolated from its environment for many millions of years. (authors)

Hazardous waste disposal sites: Report 2

International Nuclear Information System (INIS)

1979-12-01

Arkansas, like virtually every other state, is faced with a deluge of hazardous waste. There is a critical need for increased hazardous waste disposal capacity to insure continued industrial development. Additionally, perpetual maintenance of closed hazardous waste disposal sites is essential for the protection of the environment and human health. Brief descriptions of legislative and regulatory action in six other states are provided in this report. A report prepared for the New York State Environmental Facilities Corp. outlines three broad approaches states may take in dealing with their hazardous waste disposal problems. These are described. State assistance in siting and post-closure maintenance, with private ownership of site and facility, appears to be the most advantageous option

Ultimate disposal: a plan for achievement

International Nuclear Information System (INIS)

Bartlett, J.W.

1975-01-01

Four major topics relevant to R and D plans for disposal were: functions of planning, plans development procedures, R and D program procedures, and R and D plans content. Comments on these topics emphasize four major points: plans and their results support decisions on disposal methods; decisions will winnow options on the basis of comprehensive assessments; the R and D plan for disposal will be comprehensive and maintain options; time frame for the R and D program may be about 20 years. Prior and on-going work has provided a good foundation for this planning effort and the content of the plans. The R and D plans are expected to be developed this year and updated periodically

Self-disposal option for heat-generating waste - 59182

International Nuclear Information System (INIS)

Ojovan, Michael I.; Poluektov, Pavel P.; Kascheev, Vladimir A.

2012-01-01

Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered in the 70's as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste problem and is associated with the renaissance of nuclear industry. Self- disposal option utilises the heat generated by decaying radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow the capsule to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes), sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides to provide partial melting of surrounding rock. Estimates show that extreme depths of several tens and up to hundred km can be reached by capsules which could never be achieved by other techniques. Self- disposal does not require complex and expensive disposal facilities and provides a minimal footprint used only at operational stage. It has also an extremely high non- proliferation character and degree of safety. Utilisation of heat generated by relatively short-lived radionuclides diminishes the environmental uncertainties of self-disposal and increases the safety of this concept. Self-sinking heat-generating capsules could be launched from the bottom of the sea as

Determining the future for irradiated graphite disposal

International Nuclear Information System (INIS)

Neighbour, G.B.; Wickham, A.J.; Hacker, P.J.

2000-01-01

In recent years, proposals have been made for the long-term treatment of radioactive graphite waste which have ranged from sea dumping through incineration to land-based disposal, sometimes preceded by a variable period of 'safe storage' within the original reactor containment. Nuclear regulators are challenging the proposed length of 'safe storage' on the basis that essential knowledge may be lost. More recently, political constraints have further complicated the issue by eliminating disposal at sea and imposing a 'near-zero release' philosophy, while public opinion is opposed to land-based disposal and has induced a continual drive towards minimizing radioactivity release to the environment from disposal. This paper proposes that, despite various international agreements, it is time to review technically all options for disposal of irradiated graphite waste as a framework for the eventual decision-making process. It is recognized that the socio-economic and political pressures are high and therefore, given that all currently identified options satisfy the present safety limits, the need to minimize the objective risk is shown to be a minor need in comparison to the public's want of demonstrable control, responsiveness and ability to reverse/change the disposal options in the future. Further, it is shown that the eventual decision-making process for a post-dismantling option for graphite waste must optimize the beneficial attributes of subjective risk experienced by the general public. In addition, in advocating and preferred option to the general public, it is recommended that the industry should communicate at a level commensurate with the public understanding and initiate a process of facilitation which enables the public to arrive at their own solution and constituting a social exchange. Otherwise it is concluded that if the indecision over disposal options is allowed to continue then, by default, graphite will remain in long-term supervised storage. (author)

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Description of the disposal system 2012

International Nuclear Information System (INIS)

2012-12-01

Description of the Disposal System sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective presenting the initial state of the disposal system for the safety case for the disposal of spent nuclear fuel at Olkiluoto, Finland. Disposal system is an entity composed of a repository system and surface environment. The repository system includes the spent nuclear fuel, canister, buffer, backfill, and closure components as well as the host rock. The repository system components have assigned safety functions (except for the spent nuclear fuel) and are subject to requirements. The initial state is presented for each component, and references to the main supporting reports are given to guide the reader for more details. Conditions for each component vary in time and space, due to the time of emplacement and due to the tolerances set for the compositions, geometries and other properties depending on the component. The disposal operation is foreseen to commence ∼ 2020. At the beginning of the postclosure period, around 2120, all the engineered components have been installed and the operation is finalised. The system evolution during the operational phase is discussed in detail in Performance Assessment. The initial state for the host rock is defined to be essentially equal to the baseline conditions prior to starting the construction of the underground characterisation facility ONKALO. For the surface environment, the initial state is the present conditions prevailing. For any other component of the disposal system, the initial state is defined as the state it has when the direct control over that specific part of the system ceases and only limited information can be made available on the subsequent development of conditions in that part of the system or its near field. (orig.)

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Description of the disposal system 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

Description of the Disposal System sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective presenting the initial state of the disposal system for the safety case for the disposal of spent nuclear fuel at Olkiluoto, Finland. Disposal system is an entity composed of a repository system and surface environment. The repository system includes the spent nuclear fuel, canister, buffer, backfill, and closure components as well as the host rock. The repository system components have assigned safety functions (except for the spent nuclear fuel) and are subject to requirements. The initial state is presented for each component, and references to the main supporting reports are given to guide the reader for more details. Conditions for each component vary in time and space, due to the time of emplacement and due to the tolerances set for the compositions, geometries and other properties depending on the component. The disposal operation is foreseen to commence {approx} 2020. At the beginning of the postclosure period, around 2120, all the engineered components have been installed and the operation is finalised. The system evolution during the operational phase is discussed in detail in Performance Assessment. The initial state for the host rock is defined to be essentially equal to the baseline conditions prior to starting the construction of the underground characterisation facility ONKALO. For the surface environment, the initial state is the present conditions prevailing. For any other component of the disposal system, the initial state is defined as the state it has when the direct control over that specific part of the system ceases and only limited information can be made available on the subsequent development of conditions in that part of the system or its near field. (orig.)

Minimizing generator liability while disposing hazardous waste

International Nuclear Information System (INIS)

Canter, L.W.; Lahlou, M.; Pendurthi, R.P.

1991-01-01

Potential liabilities associated with hazardous waste disposal are related to waste properties, disposal practices and the potential threat to people and the environment in case of a pollutant release. Based on various regulations, these liabilities are enforceable and longstanding. A methodology which can help hazardous waste generators select a commercial disposal facility with a relatively low risk of potential liability is described in this paper. The methodology has two parts. The first part has 8 categories encompassing 30 factors common to all facilities, and the second part includes one category dealing with 5 factors on specific wastes and treatment/disposal technologies. This two-part evaluation feature enables the user to adapt the methodology to any type of waste disposal. In determining the scores for the factors used in the evaluation. an unranked paired comparison technique with slight modifications was used to weight the relative importance of the individual factors. In the methodology it is possible for the user to redefine the factors and change the scoring system. To make the methodology more efficient, a user-friendly computer program has been developed; the computer program is written so that desired changes in the methodology can be readily implemented

Draft Geologic Disposal Requirements Basis for STAD Specification

Energy Technology Data Exchange (ETDEWEB)

Ilgen, Anastasia G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-03-25

This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.

Principles and guidelines for radioactive waste disposal facilities

International Nuclear Information System (INIS)

1988-06-01

Four basic principles relevant to radioactive waste disposal identified. These principles cover the justification of the activity giving rise to the waste, the consideration of risk to present and future generations, the minimization of the need for intervention in the future, and the financial obligations of the licensee. The use of risk limits as opposed to dose limits associated with disposal is discussed, as are the concepts of critical group, de minimis, and ALARA, in the context of a waste disposal facility. Guidance is given on the selection of the preferred waste disposal concept from among several alternatives, and for judging proposed design improvements to the chosen concept

Optimization of uranium mill tailings disposal practices

International Nuclear Information System (INIS)

Richardson, Allan C.B.; Rowe, William D.

1984-01-01

So far as we have been to discern, no uranium mill tailings pile has yet been properly stabilized for long-term disposal. And although considerable effort is now being directed at developing practical solutions and at establishing standards for permanent disposal, the difficulties in application are diverse. They arise from the variety of environments in which milling is conducted, the significant costs associated with disposing of the large volumes of materials involved, the diverse nature of the hazards to be protected against, and uncertainties in both performance of controls and in how to determine societal responsibilities for management of the long term hazards to human populations from uranium tailings. There are 24 uranium tailings piles in the United States which no longer have responsible owners, and must now be disposed of by the U.S. Government in order to protect public health

Mixed waste disposal facilities at the Savannah River Site

International Nuclear Information System (INIS)

Wells, M.N.; Bailey, L.L.

1991-01-01

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission

Landfill disposal risk assessment

International Nuclear Information System (INIS)

Mininni, G.; Passino, R.; Spinosa, L.

1993-01-01

Landfill disposal is the most used waste disposal system in Italy, due to its low costs and also to the great opposition of populations towards new incineration plants and the adjustment of the existing ones. Nevertheless, landfills may present many environmental problems as far as leachate and biogas are concerned directly influencing water, air and soil. This paper shows the most important aspects to be considered for a correct evaluation of environmental impacts caused by a landfill of urban wastes. Moreover, detection systems for on site control of pollution phenomena are presented and some measures for an optimal operation of a landfill are suggested

Performance assessment for underground radioactive waste disposal systems

International Nuclear Information System (INIS)

1985-01-01

A waste disposal system comprises a number of subsystems and components. The performance of most systems can be demonstrated only indirectly because of the long period that would be required to test them. This report gives special attention to performance assessment of subsystems within the total waste disposal system, and is an extension of an IAEA report on Safety Assessment for the Underground Disposal of Radioactive Wastes

Implementation and responsibility for waste disposal : AEC sets up frameworks

International Nuclear Information System (INIS)

Anon.

1985-01-01

The Atomic Energy Commission approved the report ''measures for treatment and disposal of radioactive waste'' made by its advisory committee; which clarifies where the legal responsibility lies in relation to the waste treatment and disposal. In principle, the waste producers, i.e. the electric power companies should be responsible for the treatment and disposal of low-level radioactive waste and the Government for regulation of the safety of waste management. Then, in connection with a LLW ultimate storage facility planned in Aomori Prefecture, the waste disposal company may be responsible for safety of the LLW management. The disposal of high-level radioactive waste is the responsibility of the Government, the waste producer being responsible for the cost. Contents are the following: organization and responsibility for treatment and disposal of radioactive waste; concept of disposal of TRU waste. (Mori, K.)

The development of international safety standards on geological disposal

International Nuclear Information System (INIS)

McCartin, T.

2005-01-01

The IAEA is developing a set of safety requirements for geologic disposal to be used by both developers and regulators for planning, designing, operating, and closing a geologic disposal facility. Safety requirements would include quantitative criteria for assessing safety of geologic disposal facilities as well as requirements for development of the facility and the safety strategy including the safety case. Geologic disposal facilities are anticipated to be developed over a period of at least a few decades. Key decisions, e.g., on the disposal concept, siting, design, operational management and closure, are expected to be made in a series of steps. Decisions will be made based on the information available at each step and the confidence that may be placed in that information. A safety strategy is important for ensuring that at each step during the development of the disposal facility, an adequate understanding of the safety implications of the available options is developed such that the ultimate goal of providing an acceptable level of operational and post closure safety will be met. A safety case for a geologic disposal facility would present all the safety relevant aspects of the site, the facility design and the managerial and regulatory controls. The safety case and its supporting assessments illustrates the level of protection provided and shall give reasonable assurance that safety standards will be met. Overall, the safety case provides confidence in the feasibility of implementing the disposal system as designed, convincing estimates of the performance of the disposal system and a reasonable assurance that safety standards will be met. (author)

Radiological protection criteria risk assessments for waste disposal options

International Nuclear Information System (INIS)

Hill, M.D.

1982-01-01

Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

Americium product solidification and disposal

International Nuclear Information System (INIS)

Mailen, J.C.; Campbell, D.O.; Bell, J.T.; Collins, E.D.

1987-01-01

The americium product from the TRUEX processing plant needs to be converted into a form suitable for ultimate disposal. An evaluation of the disposal based on safety, number of process steps, demonstrated operability of the processes, production of low-level alpha waste streams, and simplicity of maintenance with low radiation exposures to personnel during maintenance, has been made. The best process is to load the americium on a cation exchange resin followed by calcination or oxidation of the resin after loading

Swiss guideline: Protection objectives for the disposal of radioactive waste

International Nuclear Information System (INIS)

Zurkinden, A.

1994-01-01

The Swiss guideline R-21 establishing the protection objectives for the disposal of radioactive waste has been reviewed and amended in order to adapt it to improvements made in the field of radioactive waste disposal. In an introductory part, the new guideline states the overall objective of radioactive waste disposal and the associated principles which have to be observed. The guideline then establishes the safety requirements applied to a geological disposal facility. These safety requirements are formulated as protection goals for the whole disposal system and not as specific criteria applying to the system components. The guideline gives finally a series of explanatory comments and indications concerning the conduct of the safety assessment for a disposal facility

Defense waste salt disposal at the Savannah River Plant

International Nuclear Information System (INIS)

Langton, C.A.; Dukes, M.D.

1984-01-01

A cement-based waste form, saltstone, has been designed for disposal of Savannah River Plant low-level radioactive salt waste. The disposal process includes emplacing the saltstone in engineered trenches above the water table but below grade at SRP. Design of the waste form and disposal system limits the concentration of salts and radionuclides in the groundwater so that EPA drinking water standards will not be exceeded at the perimeter of the disposal site. 10 references, 4 figures, 3 tables

Disposal facility for radioactive wastes

International Nuclear Information System (INIS)

Utsunomiya, Toru.

1985-01-01

Purpose: To remove heat generated from radioactive wastes thereby prevent the working circumstances from being worsened in a disposal-facility for radioactive wastes. Constitution: The disposal-facility comprises a plurality of holes dug out into the ground inside a tunnel excavated for the storage of radioactive wastes. After placing radioactive wastes into the shafts, re-filling materials are directly filled with a purpose of reducing the dosage. Further, a plurality of heat pipes are inserted into the holes and embedded within the re-filling materials so as to gather heat from the radioactive wastes. The heat pipes are connected to a heat exchanger disposed within the tunnel. As a result, heating of the solidified radioactive wastes itself or the containing vessel to high temperature can be avoided, as well as thermal degradation of the re-filling materials and the worsening in the working circumstance within the tunnel can be overcome. (Moriyama, K.)

Bibliography on ocean waste disposal. second edition. Final report 1976

International Nuclear Information System (INIS)

Stanley, H.G.; Kaplanek, D.W.

1976-09-01

This research bibliography is restricted to documents relevant to the field of ocean waste disposal. It is primarily limited to recent publications in the categories of: ocean waste disposal; criteria; coastal zone management; monitoring; pollution control; dredge spoil; dredge spoin disposal; industrial waste disposal; radioactive waste; oil spills; bioassay; fisheries resources; ocean incineration; water chemistry; and, Water pollution

Final disposal of high levels waste and spent nuclear fuel

International Nuclear Information System (INIS)

Gelin, R.

1984-05-01

Foreign and international activities on the final disposal of high-level waste and spent nuclear fuel have been reviewed. A considerable research effort is devoted to development of acceptable disposal options. The different technical concepts presently under study are described in the report. Numerous studies have been made in many countries of the potential risks to future generations from radioactive wastes in underground disposal repositories. In the report the safety assessment studies and existing performance criteria for geological disposal are briefly discussed. The studies that are being made in Canada, the United States, France and Switzerland are the most interesting for Sweden as these countries also are considering disposal into crystalline rocks. The overall time-tables in different countries for realisation of the final disposal are rather similar. Normally actual large-scale disposal operations for high-level wastes are not foreseen until after year 2000. In the United States the Congress recently passed the important Nuclear Waste Policy Act. It gives a rather firm timetable for site-selection and construction of nuclear waste disposal facilities. According to this act the first repository for disposal of commercial high-level waste must be in operation not later than in January 1998. (Author)

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

International Nuclear Information System (INIS)

Radulesscu, G.; Tang, J.S.

2000-01-01

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M andO [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M andO 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M andQ 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M andO 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

Energy Technology Data Exchange (ETDEWEB)

G. Radulesscu; J.S. Tang

2000-06-07

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable

A new procedure for deep sea mining tailings disposal

NARCIS (Netherlands)

Ma, W.; Schott, D.L.; Lodewijks, G.

2017-01-01

Deep sea mining tailings disposal is a new environmental challenge related to water pollution, mineral crust waste handling, and ocean biology. The objective of this paper is to propose a new tailings disposal procedure for the deep sea mining industry. Through comparisons of the tailings disposal

Safety assessment for radiactive waste disposal

International Nuclear Information System (INIS)

Lewi, J.; Izabel, C.

1989-11-01

Whatever their type may be, radioactive waste disposals obey to the following principle: to isolate radioactive substances as long as their potential nocivity is significant. The isolation is obtained by confining barriers. The present paper recalls the role and the limits of the different barriers, for each type of disposal. It presents and comments site selection criteria and waste packages requirements [fr

The politics of nuclear-waste disposal

International Nuclear Information System (INIS)

Tarricone, P.

1994-01-01

After 72 days of public hearings and testimony from more than 100 witnesses, the first commission of its kind in the US found that politics--not science and engineering--led to the selection of Martinsville, Ill. as the host site for a nuclear-waste-disposal facility. This article examines how the plan to dispose of nuclear waste in Martinsville ultimately unraveled

Disposal of high-activity nuclear wastes

International Nuclear Information System (INIS)

Hamilton, E.I.

1983-01-01

A discussion is presented on the deep sea ocean disposal for high-activity nuclear wastes. The following topics are covered: effect of ionizing radiation on marine ecosystems; pathways by which radionuclides are transferred to man from the marine environment; information about releases of radioactivity to the sea; radiological protection; storage and disposal of radioactive wastes and information needs. (U.K.)

Device for the disposal of radioactive liquid wastes

International Nuclear Information System (INIS)

Tomizawa, Toshi; Inoue, Tadashi.

1976-01-01

Object: To adsorb and collect radioactive nuclide ions contained in the radioactive liquid waste to select and separate thereof. Structure: A unitary disposing tank comprises an insulative cylindrical tank, an unsoluble cathode plate positioned thereunder and formed with a number of liquid inlet holes, an adsorbent layer filled with unsoluble electrically conductive substances having a large surface area in contact with the cathode plate, and an unsoluble anode plate positioned at the upper part of the cylindrical disposing tank so as not to come into contact with the adsorbent layer and formed with a number of liquid inlets, whereby one or more disposing tanks are stacked in a layer fashion, and a DC voltage is applied between the anode and cathode plates to flow a liquid to be disposed into the disposing tanks so that the radioactive metal ion nuclide in the liquid may be adsorbed and collected by the cathode and the adsorbent layer for selection and separation. (Ohara, T.)

Fee structures for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Sutherland, A.A.; Baird, R.D.; Rogers, V.C.

1988-01-01

Some compacts and states require that the fee system at their new low-level waste (LLW) disposal facility be based on the volume and radioactive hazard of the wastes. The fee structure discussed in this paper includes many potential fee elements that could be used to recover the costs of disposal and at the same time influence the volume and nature of waste that arrives at the disposal facility. It includes a base fee which accounts for some of the underlying administrative costs of disposal, and a broad range of charges related to certain parameters of the waste, such as volume, radioactivity, etc. It also includes credits, such as credits for waste with short-lived radionuclides or superior waste forms. The fee structure presented should contain elements of interest to all states and compacts. While no single disposal facility is likely to incorporate all of the elements discussed here in its fee structure, the paper presents a fairly exhaustive list of factors worth considering

Uncanistered Spent Nuclear fuel Disposal Container System Description Document

International Nuclear Information System (INIS)

Pettit, N. E.

2001-01-01

The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident

Deep injection disposal of liquid radioactive waste in Russia

International Nuclear Information System (INIS)

Foley, M.G.; Ballou, L.; Rybal'chenko, A.I.; Pimenov, M.K.; Kostin, P.P.

1998-01-01

Originally published in Russian, Deep Injection Disposal is the most comprehensive account available in the West of the Soviet and Russian practice of disposing of radioactive wastes into deep geological formations. It tells the story of the first 40 years of work in the former Soviet Union to devise, test, and execute a program to dispose by deep injection millions of cubic meters of liquid radioactive wastes from nuclear materials processing. The book explains decisions involving safety aspects, research results, and practical experience gained during the creation and operation of disposal systems. Deep Injection Disposal will be useful for studying other problems worldwide involving the economic use of space beneath the earth's surface. The material in the book is presented with an eye toward other possible applications. Because liquid radioactive wastes are so toxic and the decisions made are so vital, information in this book will be of great interest to those involved in the disposal of nonradioactive waste

Cost calculation and financial measures for high-level waste disposal business

International Nuclear Information System (INIS)

Sekiguchi, Hiromasa.

1987-01-01

A study is made on the costs for disposal of high-level wastes, centering on financial problems involving cost calculation for disposal business and methods and systems for funding the business. The first half of the report is focused on calculation of costs for disposal business. Basic equations are shown to calculate the total costs required for a disposal plant and the costs for disposal of one unit of high-level wastes. A model is proposed to calculate the charges to be paid by electric power companies to the plant for disposal of their wastes. Another equation is derived to calculate the disposal charge per kWh of power generation in a power plant. The second half of the report is focused on financial measures concerning expenses for disposal. A financial basis should be established for the implementation of high-level waste disposal. It is insisted that a reasonable method for estimating the disposal costs should be set up and it should be decided who will pay the expenses. Discussions are made on some methods and systems for funding the disposal business. An additional charge should be included in the electricity bill to be paid by electric power users, or it should be included in tax. (Nogami, K.)

Inspection and verification of waste packages for near surface disposal

International Nuclear Information System (INIS)

2000-01-01

Extensive experience has been gained with various disposal options for low and intermediate level waste at or near surface disposal facilities. Near surface disposal is based on proven and well demonstrated technologies. To ensure the safety of near surface disposal facilities when available technologies are applied, it is necessary to control and assure the quality of the repository system's performance, which includes waste packages, engineered features and natural barriers, as well as siting, design, construction, operation, closure and institutional controls. Recognizing the importance of repository performance, the IAEA is producing a set of technical publications on quality assurance and quality control (QA/QC) for waste disposal to provide Member States with technical guidance and current information. These publications cover issues on the application of QA/QC programmes to waste disposal, long term record management, and specific QA/QC aspects of waste packaging, repository design and R and D. Waste package QA/QC is especially important because the package is the primary barrier to radionuclide release from a disposal facility. Waste packaging also involves interface issues between the waste generator and the disposal facility operator. Waste should be packaged by generators to meet waste acceptance requirements set for a repository or disposal system. However, it is essential that the disposal facility operator ensure that waste packages conform with disposal facility acceptance requirements. Demonstration of conformance with disposal facility acceptance requirements can be achieved through the systematic inspection and verification of waste packages at both the waste generator's site and at the disposal facility, based on a waste package QA/QC programme established by the waste generator and approved by the disposal operator. However, strategies, approaches and the scope of inspection and verification will be somewhat different from country to country

When is a medicine unwanted, how is it disposed, and how might safe disposal be promoted? Insights from the Australian population.

Science.gov (United States)

Bettington, Emilie; Spinks, Jean; Kelly, Fiona; Gallardo-Godoy, Alejandra; Nghiem, Son; Wheeler, Amanda J

2017-12-19

Objective The aim of the present study was to explore disposal practices of unwanted medicines in a representative sample of Australian adults, compare this with previous household waste surveys and explore awareness of the National Return and Disposal of Unwanted Medicines (RUM) Project. Methods A 10-min online survey was developed, piloted and conducted with an existing research panel of adult individuals. Survey questions recorded demographics, the presence of unwanted medicines in the home, medicine disposal practices and concerns about unwanted medicines. Descriptive statistical analyses and rank-ordered logit regression were conducted. Results Sixty per cent of 4302 respondents reported having unwanted medicines in their household. Medicines were primarily kept just in case they were needed again and one-third of these medicines were expired. Two-thirds of respondents disposed of medicines with the household garbage and approximately one-quarter poured medicines down the drain. Only 17.6% of respondents had heard of the RUM Project, although, once informed, 91.7% stated that they would use it. Respondents ranked the risk of unintended ingestion as the most important public health message for future social marketing campaigns. Conclusions Respondents were largely unaware of the RUM Project, yet were willing to use it once informed. Limited awareness could lead to environmental or public health risks, and targeted information campaigns are needed. What is known about the topic? There is a growing international evidence base on how people dispose of unwanted medicines and the negative consequences, particularly the environmental effects of inappropriate disposal. Although insight into variation in disposal methods is increasing, knowledge of how people perceive risks and awareness of inappropriate disposal methods is more limited. What does this paper add? This study provides evidence of inappropriate medicines disposal and potential stockpiling of medicines in

Economic analysis of alternative LLW disposal methods

International Nuclear Information System (INIS)

Foutes, C.E.

1987-01-01

The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were developed and input into the analysis. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. Total costs of each level of a standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, was calculated for each alternative standard. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis

Shielding design of disposal container for disused sealed radioactive source

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk Hoon; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of)

2017-06-15

Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised.

Shielding design of disposal container for disused sealed radioactive source

International Nuclear Information System (INIS)

Kim, Suk Hoon; Kim, Ju Youl

2017-01-01

Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised