49 CFR 604.21 - Special considerations for advisory opinions.

Science.gov (United States)

2010-10-01

... Desist Orders § 604.21 Special considerations for advisory opinions. Based on new facts involving significant financial considerations, the Chief Counsel may take appropriate enforcement action contrary to an... 49 Transportation 7 2010-10-01 2010-10-01 false Special considerations for advisory opinions. 604...

Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

International Nuclear Information System (INIS)

2003-08-01

Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a high potential risk to workers and to the public. The IAEA has received numerous requests for assistance from Member States faced with the problem of safely managing disused sealed sources. The requests have related to both technical and safety aspects. Particularly urgent requests have involved emergency situations arising from unsafe storage conditions and lost sources. There is therefore an important requirement for the development of safe and cost-effective final disposal solutions. Consequently, a number of activities have been initiated by the IAEA to assist Member States in the management of disused sealed sources. The objective of this report is to address safety issues relevant to the disposal of disused sealed sources, and other limited amounts of radioactive waste, in borehole facilities. It is the first in a series of reports aiming to provide an indication of the present issues related to the use of borehole disposal facilities to safely disposal

International Legal and Political Considerations Concerning the Seabed Disposal of Nuclear Waste

International Nuclear Information System (INIS)

Eaker, L.H.

1983-01-01

From its beginnings in 1973, to the present time, the concept of disposing of high-level nuclear wastes within the seabed has attracted serious investigation by numerous scientists. The scientific work to date has led to the general conclusion that the burial of high-level nuclear waste within the deep-sea clays of the oceanic basins, in conjunction with a perfected multi-barrier containment concept, could prove technically and environmentally feasible. This article discusses the need for further consideration of the international legal and political implications arising from any proposed seabed disposal of high-level nuclear waste. Further consideration of the international legal issues necessarily involves the analysis of three general areas of international law, namely: the question of coverage under the 1972 London Ocean Dumping Convention; the application and effect of the provisions of the new United Nations Convention on the Law of the Sea; and the consideration of general principles of international law. (NEA) [fr

Technical considerations in the design of near surface disposal facilities for radioactive waste

International Nuclear Information System (INIS)

2001-11-01

Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

Economic considerations/comparisons for the disposal of defense high-level waste

International Nuclear Information System (INIS)

Leclaire, D.B.; Lazur, E.G.

1985-01-01

This paper provides a summary, in a generic sense, of the economic considerations and comparisons of permanent isolation of defense high-level waste (DHLW) in a licensed geologic repository. Topics considered include underground disposal, economic analysis, comparative evaluations, national defense, radioactive waste facilities, and licensing

Considerations for closure of low-level radioactive waste engineered disposal facilities

International Nuclear Information System (INIS)

1992-01-01

Proper stabilization and closure of low-level radioactive waste disposal facilities require detailed planning during the early stages of facility development. This report provides considerations for host States, compact regions, and unaffiliated States on stabilization and closure of engineered low-level radioactive waste and mixed waste disposal facilities. A time line for planning closure activities, which identifies closure considerations to be addressed during various stages of a facility's development, is presented. Current Federal regulatory requirements and guidance for closure and post-closure are outlined. Significant differences between host State and Federal closure requirements are identified. Design features used as stabilization measures that support closure, such as waste forms and containers, backfill materials, engineered barrier systems, and site drainage systems, are described. These design features are identified and evaluated in terms of how they promote long-term site stability by minimizing water infiltration, controlling subsidence and surface erosion, and deterring intrusion. Design and construction features critical to successful closure are presented for covers and site drainage. General considerations for stabilization and closure operations are introduced. The role of performance and environmental monitoring during closure is described

On the disposal of solid radioactive wastes at hospitals

International Nuclear Information System (INIS)

Rogge, B.; Lewe, P.

1987-01-01

The disposal of radioactive materials in hospitals represents a considerable problem from the point of view of economics and organisation as well as from the point of view of radiological safety. On the one-hand, groups of people (nursing personal and clean-up crews) are involved in the handling of contaminated materials who can be instructed in special handling procedures only to a limited degree with the result that simple and clear procedures must be developed; on the other hand, such simply structured routes of disposal result in enormous volumes of radioactive waste, which represent a considerable cost factor. At the Offenbach City Hospital a concept has been created which takes these problems into account. It consists of nuclide-specific collection in groups, reduction of volume by breaking up of materials, interim storage, and government approved disposal as special hospital waste materials. (orig.) [de

SPECIAL ANALYSIS FOR SLIT TRENCH DISPOSAL OF THE REACTOR PROCESS HEAT EXCHANGERS

Energy Technology Data Exchange (ETDEWEB)

Hamm, L.; Collard, L.; Aleman, S.; Gorensek, M.; Butcher, T.

2012-06-18

The Savannah River National Laboratory (SRNL), in response to a request from Solid Waste Management (SWM), conducted a Special Analysis (SA) to evaluate the performance of nineteen heat exchangers that are to be disposed in the E-Area low level waste facility Slit Trench 9 (ST 9). Although these nineteen heat exchangers were never decontaminated, the majority of the radionuclides in the heat exchanger inventory list were determined to be acceptable for burial because they are less than the 'generic' waste form inventory limits given in the 2008 Performance Assessment (PA) (WSRC, 2008). However, as generic waste, the H-3 and C-14 inventories resulted in unacceptable sum-of-fractions (SOFs). Initial scoping analyses performed by SRNL indicated that if alterations were made to certain external nozzles to mitigate various potential leak paths, acceptable SOFs could be achieved through the use of a 'Special' waste form. This SA provides the technical basis for this new 'Special' waste form and provides the inventory limits for H-3 and C-14 for these nineteen heat exchangers such that the nineteen heat exchangers can be disposed in ST 9. This 'Special' waste form is limited to these nineteen heat exchangers in ST 9 and applies for H-3 and C-14, which are designated as H-3X and C-14X, respectively. The SA follows the same methodology used in the 2008 PA and the 2008 SA except for the modeling enhancements noted below. Infiltration rates above the heat exchangers are identical to those used in the 2008 PA; however, flow through the heat exchangers is unique. Because it is unknown exactly how sealed heat exchanger openings will perform and how surface and embedded contaminants will be released, multiple base cases or scenarios were established to investigate a set of performances. Each scenario consists of flow options (based on the performance of sealed openings) and a near-field release of contaminants (based on corrosion and

Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

International Nuclear Information System (INIS)

Galkin, A.V.; Baldov, A.N.

2001-01-01

In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

Preliminary consideration for research on geological disposal of high-level radioactive waste in China in the period of 2000-2040

International Nuclear Information System (INIS)

Xu Guoqing

2004-01-01

Based on the overseas practical experiences with combination of domestic realistic conditions a preliminary consideration of a long-range plan is proposed for research on geological disposal of high-level radioactive waste in China in the period of 2000-2040. An overview of research on geological disposal of high-level radioactive waste in the overseas and mainland is presented shortly first in this paper. Then the discussion is centered on the preliminary consideration of a long-range plan for research on geological disposal of high-level radioactive waste in China. The partition of stages of research on geological disposal of high-level radioactive waste, the goal, task, research contents and time table for each research stage is stated in this preliminary consideration. The data mentioned above will probably be useful for making plan for geological disposal of high-level radioactive waste in the future in China. (author)

Special Analysis: Disposal Plan for Pit 38 at Technical Area 54, Area G

Energy Technology Data Exchange (ETDEWEB)

French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [URS Coporation

2012-06-26

been made to utilize the remaining disposal capacity within MDA G to the greatest extent possible. One approach for doing this has been to dispose of low-activity waste from cleanup operations at LANL in the headspace of selected disposal pits. Waste acceptance criteria (WAC) for the material placed in the headspace of pits 15, 37, and 38 have been developed (LANL, 2010) and the impacts of placing waste in the headspace of these units has been evaluated (LANL, 2012a). The efforts to maximize disposal efficiency have taken on renewed importance because of the disposal demands placed on MDA G by the large volumes of waste that are being generated at LANL by cleanup efforts. For example, large quantities of waste were recently generated by the retrieval of waste formerly disposed of at TA-21, MDA B. A portion of this material has been disposed of in the headspace of pit 38 in compliance with the WAC developed for that disposal strategy; a large amount of waste has also been sent to off-site facilities for disposal. Nevertheless, large quantities of MDA B waste remain that require disposal. An extension of pit 38 was proposed to provide the disposal capacity that will be needed to dispose of institutional waste and MDA B waste through 2013. A special analysis was prepared to evaluate the impacts of the pit extension (LANL, 2012b). The analysis concluded that the disposal unit could be extended with modest increases in the exposures projected for the Area G performance assessment and composite analysis, as long as limits were placed on the radionuclide concentrations in the waste that is placed in the headspace of the pit. Based, in part, on the results of the special analysis, the extension of pit 38 was approved and excavation of the additional disposal capacity was started in May 2012. The special analysis presented here uses performance modeling to identify a disposal plan for the placement of waste in pit 38. The modeling uses a refined design of the disposal unit and

Special Analysis: Disposal Plan for Pit 38 at Technical Area 54, Area G

International Nuclear Information System (INIS)

French, Sean B.; Shuman, Rob

2012-01-01

have been made to utilize the remaining disposal capacity within MDA G to the greatest extent possible. One approach for doing this has been to dispose of low-activity waste from cleanup operations at LANL in the headspace of selected disposal pits. Waste acceptance criteria (WAC) for the material placed in the headspace of pits 15, 37, and 38 have been developed (LANL, 2010) and the impacts of placing waste in the headspace of these units has been evaluated (LANL, 2012a). The efforts to maximize disposal efficiency have taken on renewed importance because of the disposal demands placed on MDA G by the large volumes of waste that are being generated at LANL by cleanup efforts. For example, large quantities of waste were recently generated by the retrieval of waste formerly disposed of at TA-21, MDA B. A portion of this material has been disposed of in the headspace of pit 38 in compliance with the WAC developed for that disposal strategy; a large amount of waste has also been sent to off-site facilities for disposal. Nevertheless, large quantities of MDA B waste remain that require disposal. An extension of pit 38 was proposed to provide the disposal capacity that will be needed to dispose of institutional waste and MDA B waste through 2013. A special analysis was prepared to evaluate the impacts of the pit extension (LANL, 2012b). The analysis concluded that the disposal unit could be extended with modest increases in the exposures projected for the Area G performance assessment and composite analysis, as long as limits were placed on the radionuclide concentrations in the waste that is placed in the headspace of the pit. Based, in part, on the results of the special analysis, the extension of pit 38 was approved and excavation of the additional disposal capacity was started in May 2012. The special analysis presented here uses performance modeling to identify a disposal plan for the placement of waste in pit 38. The modeling uses a refined design of the disposal unit

Radioactive waste and special waste disposal in salt domes - phoney waste management solutions

International Nuclear Information System (INIS)

Grimmel, E.

1990-01-01

The paper tries to make aware of the fact that an indefinite safe disposal of anthropogeneous wastes in underground repositories is impossible. Suspicion is raised that the Gorleben-Rambow salt dome has never been studied for its suitability as a repository, but that it was simply taken for granted. Safety analyses are meant only to conceal uncertainty. It is demanded to immediately opt out of the ultimate disposal technique for radioactive and special wastes in salt caverns. (DG) [de

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

40 CFR 2.305 - Special rules governing certain information obtained under the Solid Waste Disposal Act, as amended.

Science.gov (United States)

2010-07-01

... information obtained under the Solid Waste Disposal Act, as amended. 2.305 Section 2.305 Protection of... § 2.305 Special rules governing certain information obtained under the Solid Waste Disposal Act, as amended. (a) Definitions. For purposes of this section: (1) Act means the Solid Waste Disposal Act, as...

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

Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, Sandra M.

1997-01-01

Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

Design considerations for sealing the shafts of a nuclear fuel waste disposal vault

International Nuclear Information System (INIS)

Mortazavi, M.H.S.; Chan, H.T.; Radhakrishna, H.S.

1985-05-01

The shafts in an underground disposal system, which constitute potential pathways between the disposal vault and the biosphere, should be effectively sealed if the system is to perform as a hydrodynamic and geochemical barrier for the safe containment of nuclear fuel waste. In the design of the shaft backfill, consideration should be given to ensure that the backfill and the backfill/rock interface remain intact. Design-related problems, including critical pathways for the transport or radionuclides, configuration of shaft backfill and its functional requirements, the state of stress in a backfilled shaft with particular emphasis on the arching and load transfer phenomenon are discussed in this report

Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

CERN Document Server

International Atomic Energ Agency. Vienna

2003-01-01

Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a ...

Special Consideration in Post-Secondary Institutions: Trends at a Canadian University

Science.gov (United States)

Zimmermann, Joelle; Kamenetsky, Stuart B.; Pongracic, Syb

2015-01-01

This study examined trends in the practice of granting special consideration for missed tests and late papers in colleges and universities. We analyzed a database of 4,183 special consideration requests at a large Canadian university between 1998 and 2008. Results show a growing rate of requests per enrolment between 2001 and 2007. Although…

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

48 CFR 970.1504-1-9 - Special considerations: Cost-plus-award-fee.

Science.gov (United States)

2010-10-01

...: Cost-plus-award-fee. 970.1504-1-9 Section 970.1504-1-9 Federal Acquisition Regulations System... Negotiation 970.1504-1-9 Special considerations: Cost-plus-award-fee. (a) When a management and operating contract is to be awarded on a cost-plus-award-fee basis, several special considerations are appropriate...

One consideration about rational design of the multi tunnels in geological disposal facility

International Nuclear Information System (INIS)

Mizutani, Kazuhiko; Hiramoto, Masayuki; Morita, Atsushi

2008-01-01

In the geological disposal facility of the high-level radioactive waste, a group of galleries is designed in parallel at the depth of more than 300 m below surface. This is an unprecedented structure in the field of conventional engineering, and it is necessary to take this characteristic into consideration in the design of the galleries. In the geological disposal facility, as well as ensuring the dynamic stability of the gallery during construction and operational periods, it is necessary to dynamic characteristic of rock mass for long-term stability after the closure. In this study, analysis of the 'multi tunnels model' which represents the whole gallery group was performed and the results about load to act on a pillar. (author)

Geology of high-level nuclear waste disposal

International Nuclear Information System (INIS)

Roxburgh, I.S.

1988-01-01

The concept of geological disposal is set out by describing the major rock types in terms of their ability to isolate high-level nuclear waste. The advantages and problems posed by particular rock formations are explored and the design and construction of geological repositories is considered, along with the methods used to estimate their safety. It gives special consideration to the use of sea-covered rock and sediment as well as the on-land situation. Throughout the book the various principles and problems inherent in geological disposal are explained and illustrated by reference to a multitude of European and North American case studies, backed up by a large number of tables, figures and an extensive bibliography

Considerations about the licensing process of special nuclear industrial facilities

Energy Technology Data Exchange (ETDEWEB)

Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2015-07-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

Considerations about the licensing process of special nuclear industrial facilities

International Nuclear Information System (INIS)

Talarico, M.A.; Melo, P.F. Frutuoso e

2015-01-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

48 CFR 915.404-4-72 - Special considerations for cost-plus-award-fee contracts.

Science.gov (United States)

2010-10-01

... cost-plus-award-fee contracts. 915.404-4-72 Section 915.404-4-72 Federal Acquisition Regulations System....404-4-72 Special considerations for cost-plus-award-fee contracts. (a) When a contract is to be awarded on a cost-plus-award-fee basis several special considerations are appropriate. Fee objectives for...

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)

Wilderness Preparticipation Evaluation and Considerations for Special Populations.

Science.gov (United States)

Joy, Elizabeth; Van Baak, Karin; Dec, Katherine L; Semakula, Barbara; Cardin, Ashlea D; Lemery, Jay; Wortley, George C; Yaron, Michael; Madden, Christopher

2015-12-01

Children, older adults, disabled and special needs athletes, and female athletes who participate in outdoor and wilderness sports and activities each face unique risks. For children and adolescents traveling to high altitude, the preparticipation physical evaluation should focus on risk assessment, prevention strategies, early recognition of altitude-related symptoms, management plans, and appropriate follow-up. As the risk and prevalence of chronic disease increases with age, both older patients and providers need to be aware of disease and medication-specific risks relative to wilderness sport and activity participation. Disabled and special needs athletes benefit from careful pre-event planning for the potential medical issues and equipment modifications that may affect their health in wilderness environments. Issues that demand special consideration for female adventurers include pregnancy, contraceptive use, menses, and ferritin levels at altitude. A careful preparticipation evaluation that factors in unique, population- specific risks will help special populations stay healthy and safe on wilderness adventures. The PubMed and SportDiscus databases were searched in 2014 using both MeSH terms and text words and include peer-reviewed English language articles from 1977 to 2014. Additional information was accessed from Web-based sources to produce this narrative review on preparticipation evaluation for special populations undertaking wilderness adventures. Key words include children, adolescent, pediatric, seniors, elderly, disabled, special needs, female, athlete, preparticipiation examination, wilderness medicine, and sports. Copyright © 2015. Published by Elsevier Inc.

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

Cost Considerations and Financing Mechanisms for the Disposal of Low and Intermediate Level Radioactive Waste

International Nuclear Information System (INIS)

2007-06-01

The overall objective of this publication is to provide Member States who are currently planning or preparing new near surface repositories for low and intermediate level radioactive waste (LILW), guidance on cost considerations and funding mechanisms for the repositories' entire life cycle. The report focuses on both technical and non-technical factors affecting repository costs. It considers the major cost elements that comprise a cost evaluation for a disposal facility for LILW and identifies those factors which may result in major uncertainties in an overall cost estimate. In particular, the report lists the basic disposal options and summarizes the legal basis and infrastructure requirements for establishing an effective financing system. It further includes the cost estimation methodology, considers the major cost categories and discusses factors to be considered when planning the financing mechanism, and describes relevant financing schemes

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)

Pectus updates and special considerations in Marfan syndrome

Directory of Open Access Journals (Sweden)

Stephanie Fraser

2018-01-01

Full Text Available Congenital chest wall or pectus deformities including pectus excavatum (funnel chest and pectus carinatum (pigeon chest affect a significant proportion of the general population and up to 70% of patients with Marfan syndrome. Patients often experience significant morbidity and psychological distress, which can worsen with age. Here we discuss new techniques for both operative and non-operative treatment of pectus deformity, the importance of a welltimed intervention and special considerations in patients with Marfan syndrome.

Special feature of the facilities for final disposal of radioactive waste and its potential impact on the licensing process

International Nuclear Information System (INIS)

Lee Gonzales, Horacio M.; Medici, Marcela A.; Alvarez, Daniela E.; Biaggio, Alfredo L.

2009-01-01

During the lifetime of a radioactive waste disposal facility it is possible to identify five stages: design, construction, operation, closure and post-closure. While the design, and pre-operation stages are, to some extent, similar to other kind of nuclear or radioactive facilities; construction, operation, closure and post-closure have quite special meanings in the case of radioactive waste disposal systems. For instance, the 'closure' stage of a final disposal facility seems to be equivalent to the commissioning stage of a conventional nuclear or radioactive facility. This paper describes the unique characteristics of these stages of final disposal systems, that lead to concluded that their licensing procedure can not be assimilated to the standard licensing procedures in use for other nuclear or radioactive facilities, making it necessary to develop a tailored license system. (author)

Present state on research and development of underground disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

In September, 1996, Power Reactor and Nuclear Fuel Development Corp. (PNC) arranged her old research and development (R and D) results to issue as a shape of `Technical report on R and D of high level radioactive waste underground disposal`. On the other hand, Radioactive waste special party in Committee of Atomic Energy at that time evaluated that technical possibility for safety establishment of underground disposal in Japan was elucidated and showed future problems in the technical development. Therefore, PNC proceeded further R and D for the second arrangement under consideration of such comments. As a result, in investigation of geological environment condition, main points were laid at study on rear-field feature and its long-term stability. In development of disposal technique, main points were laid at elucidation of design requirements confirmable to the near-field evaluation, main points were laid at upgrading validity of evaluation model to analytically evaluate the near-field feature using data with high reliability. (G.K.)

Present state on research and development of underground disposal

International Nuclear Information System (INIS)

1996-12-01

In September, 1996, Power Reactor and Nuclear Fuel Development Corp. (PNC) arranged her old research and development (R and D) results to issue as a shape of 'Technical report on R and D of high level radioactive waste underground disposal'. On the other hand, Radioactive waste special party in Committee of Atomic Energy at that time evaluated that technical possibility for safety establishment of underground disposal in Japan was elucidated and showed future problems in the technical development. Therefore, PNC proceeded further R and D for the second arrangement under consideration of such comments. As a result, in investigation of geological environment condition, main points were laid at study on rear-field feature and its long-term stability. In development of disposal technique, main points were laid at elucidation of design requirements confirmable to the near-field evaluation, main points were laid at upgrading validity of evaluation model to analytically evaluate the near-field feature using data with high reliability. (G.K.)

Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Cook, J.R.

2001-01-01

This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC

Considerations for alternative low-level radioactive disposal sites

International Nuclear Information System (INIS)

Beck, J.M.

1986-01-01

In the immediate future, there is a need for low-level radioactive disposal sites to accommodate wastes that would otherwise be placed at a later date in permanent, government sanctioned ''compact'' sites. Until these ''compact'' sites become operational, a potential, relatively low-cost alternative exists in the numerous inactive uranium processing sites that are likewise proposed for remedial action removal or stabilization operations. This paper addressed disposal from the aspects of engineering design, economics and liability of participating parties. Many uranium (and by-product) processing facilities in the western states now stand idle due to current economic conditions within the industry. Many more were previously deactivated for various reasons. All must be dealt with under the UMTRA Program Guidelines with regard to removal, reclamation or other remedial action activities. With cooperative efforts, some of these sites would appear to be suitable for disposal of small volume, low-level radioactive wastes that presently render urban properties valueless in terms of real estate and aesthetic values. Likely sites would appear to be those slated for in-place stabilization and reclamation, particularly where the urban property material has a lower level of radioactivity than the disposal site material. The resultant impacts for site stabilization and reclamation would be solely in the areas of increased material volumes (generally requiring a minimal increase in engineering design complexity) and liability. Clearly, liability will be the overriding factor in such an approach. With the complex hierarchy of regulatory agencies involved and the private sector, what appears to be a relative simple and economic approach may have extreme difficulty in achieving reality

The social and special effects of siting a low-level radioactive waste disposal facility in rural Texas

International Nuclear Information System (INIS)

Murdock, S.H.; Hamm, R.R.

1987-01-01

As part of its assessment of the impacts of a low-level radioactive waste disposal facility in Hudspeth County, the Texas Low-Level Radioactive Waste Disposal Authority (TLLRWDA) sponsored an independent study of the social and special impacts of the facility. These impacts include ''standard'' social impacts (such as impacts on social structures and attitudes, values and perceptions and ''special'' social impacts (such as fear, anxiety, concerns related to equity, the health of future generations, etc.). This paper reports the results of this study. Personal interviews with 71 community leaders and 96 randomly selected county residents were conducted during the summer of 1986. The results suggest that the major concern relates to the contamination of ground water, but that suspicion about the equity of the siting process and about the safe management of wastes is extensive, even among the most knowledgeable respondents. Mitigation concerns center on health and safety issues for residents and on potential forms of mitigation for governmental jurisdictions for leaders. Responses were similar for leaders and residents and for persons in different parts of the county

36 CFR 1237.20 - What are special considerations in the maintenance of audiovisual records?

Science.gov (United States)

2010-07-01

... considerations in the maintenance of audiovisual records? 1237.20 Section 1237.20 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION RECORDS MANAGEMENT AUDIOVISUAL, CARTOGRAPHIC, AND RELATED RECORDS MANAGEMENT § 1237.20 What are special considerations in the maintenance of audiovisual...

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

Consideration of timescales in the finnish safety regulations for spent fuel disposal

International Nuclear Information System (INIS)

Ruokola, E.

2010-01-01

has taken upon itself the identification of the impacts on the biosphere from the releases of disposed radionuclides. The Farthest Future: At about 250 000 years, the total radioactivity in spent nuclear fuel becomes very close to that in the natural uranium from which the fuel was fabricated. In this time frame, the hazard posed by a spent fuel repository will be comparable to that of a medium sized natural uranium deposit and the repository might be regarded as being part of the nature. Accordingly, for the time period beyond one million years, the regulations do not require any rigorous quantitative safety assessments but the judgement of safety can be based on more qualitative considerations, such as bounding analyses with simplified methods, comparisons with natural analogues and observations of the geological history of the site

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

Home Sewage Disposal. Special Circular 212.

Science.gov (United States)

Wooding, N. Henry

This circular provides current information for homeowners who must repair or replace existing on-lot sewage disposal systems. Site requirements, characteristics and preparation are outlined for a variety of alternatives such as elevated sand mounds, sand-lined beds and trenches, and oversized absorption area. Diagrams indicating construction…

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

Energy Technology Data Exchange (ETDEWEB)

Collard, L.B.

2000-09-26

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds.

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Collard, L.B.

2000-01-01

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds

Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, S.M.

1997-10-01

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country''s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today''s standards. This report summarizes each site''s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US

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

A consideration of retrievability in geologic disposal of radioactive wastes

International Nuclear Information System (INIS)

Sasaki, Noriaki

2001-12-01

Geologic disposal cannot be implemented based only on the consensus of the engaged technical community, and needs the wide social agreement and confidence for it. This is now a common understanding in many countries. Under this kind of recognition, the concept of retrievability in geologic disposal of radioactive wastes has been rapidly interested in recent years and has being discussed in several European countries. For example, EC has cooperated the concerted action on the retrievability of long-lived radioactive waste with the joining of nine countries, and the expert group on disposal concepts for radioactive waste (EKRA) set up by the Swiss government has presented its findings on the new concept of the long-lived radioactive waste management considering the retrievability. The OECD/NEA has also discussed on this issue and published the documents. There are some countries where the legislation requires the retrievability. This paper briefly summarizes the important findings and recommendations on the concept of retrievability, as the results of review of some interesting documents from European countries, for the purpose of reflecting to the research and development of geologic disposal in Japan. (author)

48 CFR 970.1504-1-3 - Special considerations: Laboratory management and operation.

Science.gov (United States)

2010-10-01

...: Laboratory management and operation. 970.1504-1-3 Section 970.1504-1-3 Federal Acquisition Regulations System DEPARTMENT OF ENERGY AGENCY SUPPLEMENTARY REGULATIONS DOE MANAGEMENT AND OPERATING CONTRACTS Contracting by Negotiation 970.1504-1-3 Special considerations: Laboratory management and operation. (a) For the management...

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.

Special Analysis: 2017-001 Disposal of Drums Containing Enriched Uranium in Pit 38 at Technical Area 54, Area G

Energy Technology Data Exchange (ETDEWEB)

Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-06-05

Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. This special analysis, SA 2017-001, evaluates the potential impacts of disposing of this waste in Pit 38 at Area G based on the assumptions that form the basis of the Area G PA/CA. Section 2 describes the methods used to conduct the analysis; the results of the evaluation are provided in Section 3; and conclusions and recommendations are provided in Section 4.

Student Application for Special Consideration for Examination Performance Following a Natural Disaster

Science.gov (United States)

Collings, David; Garrill, Ashley; Johnston, Lucy

2018-01-01

Universities have a long-established tradition of granting students special consideration when circumstances beyond their control negatively affect performance in assessments. Typically, such situations affect only one student (e.g. medical emergencies) but we consider the impact of a natural disaster that led to all students being eligible for…

Criticality safety considerations in the geologic disposal of spent nuclear fuel assemblies

International Nuclear Information System (INIS)

Gore, B.F.; McNair, G.W.; Heaberlin, S.W.

1980-05-01

Features of geologic disposal which hamper the demonstration that criticality cannot occur therein include possible changes of shape and form, intrusion of water as a neutron moderator, and selective leaching of spent fuel constituents. If the criticality safety of spent fuel disposal depends on burnup, independent measurements verifying the burnup should be performed prior to disposal. The status of nondestructive analysis method which might provide such verification is discussed. Calculations were performed to assess the potential for increasing the allowed size of a spent fuel disposal canister if potential water intrusion were limited by close-packing the enclosed rods. Several factors were identified which severely limited the potential of this application. The theoretical limit of hexagonal close-packing cannot be achieved due to fuel rod bowing. It is concluded that disposal canisters should be sized on the basis of assumed optimum moderation. Several topics for additional research were identified during this limited study

Operation of controlled-air incinerators and design considerations for controlled-air incinerators treating hazardous and radioactive wastes

International Nuclear Information System (INIS)

McRee, R.E.

1986-01-01

This paper reviews the basic theory and design philosophies of the so-called controlled-air incinerator and examines the features of this equipment that make it ideally suited to the application of low-level radioactive waste disposal. Special equipment design considerations for controlled air incinerators treating hazardous and radioactive wastes are presented. 9 figures

Feasibility of co-disposing low-level radioactive waste with uranium mill tailings and/or FUSRAP waste

International Nuclear Information System (INIS)

Whitman, M.

1983-09-01

Analysis of the two most critical factors affecting a co-facility, economics and technical feasibility, indicates that neither should pose significant problems and in fact many aspects, particularly in economics, favor a co-facility over specialized disposal facilities. In consideration of costs, the symbiotic nature of co-facility economics should be recognized by the different parties the co-facility would serve. By minimizing the cost burdens of the LLW/UMTRAP disposal site users, a co-facility offers a unique opportunity for the cooperative subsidization of commercial and governmental operations. Likewise, a LLW/active tailings disposal co-facility affords two different sets of commercial users the opportunity to maximize the economic efficiency of each other's disposal operations. The technical requirements for siting a LLW or uranium mill tailings disposal facility are so similar as to appear tailor-made for a co-facility. Where differences are necessary, such as to distinguish between pollution sources in environmental monitoring, LLW and mill tailings are different. Where similarities are useful, such as in siting criteria and disposal operations, LLW and mill tailings are nearly identical. Institutional factors are split in their adaptability to a co-facility. Although public perceptions will range to both extremes, the fact that a significant percentage of the local populace may favor a co-facility serves as added incentive for such an operation. The institutional aspects which could serve as considerable impediments to co-facility development would be concern about liability in the event of site failure and licensing and legal obstacles associated with UMTRAP disposal that did not meet active tailings disposal licensing requirements

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

Some considerations in the evaluation of concrete as a structural material for alternative LLW disposal technologies

International Nuclear Information System (INIS)

MacKenzie, D.R.; Siskind, B.; Bowerman, B.S.; Piciulo, P.L.

1987-01-01

The objective of this study was to develop information needed to evaluate the long-term performance of concrete and reinforced concrete as a structural material for alternative LLW disposal methods. The capability to carry out such an evaluation is required for licensing a site which employs one of these alternative methods. The basis for achieving the study objective was the review and analysis of the literature on concrete and its properties, particularly its durability. In carrying out this program characteristics of concrete useful in evaluating its performance and factors that can affect its performance were identified. The factors are both intrinsic, i.e., associated with composition of the concrete (and thus controllable), and extrinsic, i.e., due to external environmental forces such as climatic conditions and aggressive chemicals in the soil. The testing of concrete, using both accelerated tests and long-term non-accelerated tests, is discussed with special reference to its application to modeling of long-term performance prediction. On the basis of the study's results, conditions for acceptance are recommended as an aid in the licensing of disposal sites which make use of alternative methods

Greater confinement disposal of high activity and special case wastes at the Nevada Test Site: A unified migration assessment approach

International Nuclear Information System (INIS)

Davis, P.A.; Olague, N.E.; Johnson, V.L.; Dickman, P.T.; O'Neill, L.J.

1993-01-01

The Department of Energy's Nevada Field Office has disposed of a small quantity of high activity and special case wastes using Greater Confinement Disposal facilities in Area 5 of the Nevada Test Site. Because some of these wastes are transuranic radioactive wastes, the Environmental Protection Agency standards for their disposal under 40 CFR Part 191 which requires a compliance assessment. In conducting the 40 CFR Part 191 compliance assessment, review of the Greater Confinement Disposal inventory revealed potentially land disposal restricted hazardous wastes. The regulatory options for disposing of land disposal restricted wastes consist of (1) treatment and monitoring, or (2) developing a no-migration petition. Given that the waste is already buried without treatment, a no-migration petition becomes the primary option. Based on a desire to minimize costs associated with site characterization and performance assessment, a single approach has been developed for assessing compliance with 40 CFR Part 191, DOE Order 5820.2A (which regulates low-level radioactive wastes contained in Greater Confinement Disposal facilities) and developing a no-migration petition. The approach consists of common points of compliance, common time frame for analysis, and common treatment of uncertainty. The procedure calls for conservative bias of modeling assumptions, including model input parameter distributions and adverse processes and events that can occur over the regulatory time frame, coupled with a quantitative treatment of data and parameter uncertainty. This approach provides a basis for a defensible regulatory decision. In addition, the process is iterative between modeling and site characterization activities, where the need for site characterization activities is based on a quantitative definition of the most important and uncertain parameters or assumptions

Considerations of human inturison in U.S. programs for deep geologic disposal of radioactive waste.

Energy Technology Data Exchange (ETDEWEB)

Swift, Peter N.

2013-01-01

Regulations in the United States that govern the permanent disposal of spent nuclear fuel and high-level radioactive waste in deep geologic repositories require the explicit consideration of hypothetical future human intrusions that disrupt the waste. Specific regulatory requirements regarding the consideration of human intrusion differ in the two sets of regulations currently in effect in the United States; one defined by the Environmental Protection Agencys 40 Code of Federal Regulations part 197, applied only to the formerly proposed geologic repository at Yucca Mountain, Nevada, and the other defined by the Environmental Protection Agencys 40 Code of Federal Regulations part 191, applied to the Waste Isolation Pilot Plant in New Mexico and potentially applicable to any repository for spent nuclear fuel and high-level radioactive waste in the United States other than the proposed repository at Yucca Mountain. This report reviews the regulatory requirements relevant to human intrusion and the approaches taken by the Department of Energy to demonstrating compliance with those requirements.

Derivation methods for clearance levels and safety assessments for very low-level radioactive waste disposal

International Nuclear Information System (INIS)

Okoshi, Minoru

2001-01-01

The clearance level was evaluated by the dose of concrete and metal when they would be recycled and reused from shallow land burial of radioactive facilities. The state of waste after clearance is not specified, so that we studied large scale of exposure pathways. The parameter values used for safety assessment were determined as the average values under the consideration of natural and social environment in Japan. Propriety of these values was confirmed by a probability analysis. On the safety assessment of very low-level waste disposal facility, the disposer pathway and parameters were determined under the consideration of special site conditions (natural and social environment) and properties of waste. However, the same exposure pathway of them used the same model for external (exposure by sky shine' s ray) and internal exposure. The calculation results of estimated pathway showed 1.2x10 -5 mSv/y the largest dose for the external exposure pathway by sky shine's ray. (S.Y.)

Identification and characterization of Department of Energy special-case radioactive waste

International Nuclear Information System (INIS)

Williams, R.E.; Kudera, D.E.

1990-01-01

This paper identifies and characterizes Department of Energy (DOE) special-case radioactive wastes. Included in this paper are descriptions of the special-case waste categories and their volumes and curie contents, as well as discussions of potential methods for management of these special-case wastes. Work on extensive inventories of DOE-titled special-case waste are still in progress. All radioactive waste is characterized to determine its waste category. Some wastes may have characteristics of more than one of the major waste types. These characteristics may prevent such wastes from being managed as typical high-level, low-level, or transuranic waste. DOE has termed these wastes special-case wastes. Special-case wastes may require special management and disposal schemes. Because of these special considerations, DOE-Headquarters (HQ) required the identification of all existing and potential DOE-owned special case waste to determine future management planning and funding requirements. The inventory effort includes all commercially held, DOE-owned radioactive materials

Limited risk assessment and some cost/benefit considerations for greater confinement disposal compared to shallow land burial

International Nuclear Information System (INIS)

Hunter, P.H.; Lester, D.H.; Robertson, L.D.; Spaeth, M.E.; Stoddard, J.A.; Dickman, P.T.

1984-09-01

A limited risk assessment and some cost/benefit considerations of greater confinement disposal (GCD) compared to shallow land burial (SLB) are presented. This study is limited to an analysis of the postclosure phase of hypothetical GCD and SLB facilities. Selected release scenarios are used which bound the range of risks to a maximally exposed individual and a hypothetical population. Based on the scenario assessments, GCD had a significant risk advantage over SLB for normal exposure pathways at both humid and arid sites, particularly for the human intrusion scenario. Since GCD costs are somewhat higher than SLB, it is necessary to weigh the higher costs of GCD against the higher risks of SLB. In this regard, GCD should be pursued as an alternative to SLB for certain types of low-level waste, and as an alternative to processing for wastes requiring improved stabilization or higher integrity packaging to be compatible with SLB. There are two reasons for this conclusion. First, GCD might diminish public apprehension regarding the disposal of wastes perceived to be too hazardous for SLB. Second, GCD may be a relatively cost-effective alternative to various stabilization and packaging schemes required to meet 10 CFR 61 near-surface requirements as well as being a cost-effective alternative to deep geologic disposal. Radionuclide transport through the biosphere and resultant dose consequences were determined using the RADTRAN radionuclide transport code. 19 references, 4 figures, 5 tables

48 CFR 915.404-4-70-5 - Special considerations-contracts with nonprofit organizations (other than educational institutions).

Science.gov (United States)

2010-10-01

... TYPES CONTRACTING BY NEGOTIATION Contract Pricing 915.404-4-70-5 Special considerations—contracts with... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Special considerations-contracts with nonprofit organizations (other than educational institutions). 915.404-4-70-5 Section 915.404...

TYPE AF CERTIFICATE FOR TRANSPORTATION OF LOW ENRICHED URANIUM OXIDE (LEUO) FOR DISPOSAL

International Nuclear Information System (INIS)

Opperman, E; Kenneth Yates, K

2007-01-01

Washington Savannah River Company (WSRC) operates the Savannah River Site (SRS) in Aiken, SC under contract with the U.S. Department of Energy (DOE). SRS had the need to ship 227 drums of low enriched uranium oxide (LEUO) to a disposal site. The LEUO had been packaged nearly 25 years ago in U.S. Department of Transportation (DOT) 17C 55-gallon drums and stored in a warehouse. Since the 235U enrichment was just above 1 percent by weight (wt%) the material did not qualify for the fissile material exceptions in 49 CFR 173.453, and therefore was categorized as 'fissile material' for shipping purposes. WSRC evaluated all existing Type AF packages and did not identify any feasible packaging. Applying for a new Type AF certificate of compliance was considered too costly for a one-time/one-way shipment for disposal. Down-blending the material with depleted uranium (to reduce enrichment below 1 wt% and enable shipment as low specific activity (LSA) radioactive material) was considered, but appropriate blending facilities do not exist at SRS. After reviewing all options, WSRC concluded that seeking a DOT Special Permit was the best option to enable shipment of the material for permanent disposal. WSRC submitted the Special Permit application to the DOT, and after one request-for-additional-information (RAI) the permit was considered acceptable. However, in an interesting development that resulted from the DOT Special Permit application process, it was determined that it was more appropriate for the DOE to issue a Type AF certificate [Ref. 1] for this shipping campaign. This paper will outline the DOT Special Permit application and Type AF considerations, and will discuss the issuance of the new DOE Type AF certificate of compliance

Disposal of high level radioactive waste consideration of some basic criteria

International Nuclear Information System (INIS)

1993-01-01

The series of Nordic documents on radiation protection principles present the joint views of the Nordic authorities on radiation protection issues. These views are to be regarded as recommendations to the same Nordic authorities to be considered in their work on national regulations and applications. This document deals with the principles of disposal of high level radioactive waste, including spent fuels, and is therefore intended for authorities in nuclear safety as well as radiation protection. The emphasis is on radiation protection criteria, and the document is primarily directed to the authorities but can also be of interest to the nuclear power industry in its planning of disposal facilities. It can also be used as a source of information on the problems associated with high level waste and on the principles by which these problems would be solved. The main emphasis has been placed on the long-term aspects. The recommendations given by ICRP and the ideas and discussions presented by NEA and IAEA in various publications were the main documents taken into account. The discussions concentrate on the deep geological repository which is the main disposal concept currently being considered in the Nordic countries. The plans in Finland and Sweden include the selection of a disposal site around the year 2000 and a construction period in the early part of the next century. 32 refs, 3 figs

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

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

Hazard characterization and special considerations for environmental and decontamination and decommissioning activities

International Nuclear Information System (INIS)

Kerr, N.R.

1993-08-01

The mission of the US Department of Energy (DOE) has changed from defense production of special nuclear materials to cleanup of production facilities at the Hanford Site. The DOE contractors have formed the Energy Facility Contractors Group to support this change in mission. In addition, the Safety Analysis Working Subgroup for Environmental Restoration and Decontamination and Decommissioning (ER/D ampersand D) was formed to identify, develop, and share information that supports safety analyses and engineering of ER/D ampersand D activities. Safety analysis is in part the process of identifying and understanding the hazards that could result in exposures to radiological or chemical hazardous substances. The following paragraphs address the special considerations given to hazard characterization for ER/D ampersand D activities

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

Operational safety and radioprotection considerations when designing the ILW-LL disposal zone

International Nuclear Information System (INIS)

Voinis, S.; Roulet, A.; Claudel, D.; Lesavre, A.

2008-01-01

As for any other nuclear industrial facility, in a radioactive waste repository the various waste disposal operational activities from construction to closure can present a risk to human (workers and public) and the environment. In accordance with the December 30, 1991 French Waste Act, Andra has conducted feasibility studies regarding the disposal of HLW and ILW-LL waste in a clay host formation. The 'Dossier 2005 - Clay' includes a description of the operational safety analysis that was conducted for ILW-LL waste disposal in underground horizontal drifts. The objective of this paper is to present that safety analysis and its impact on the design at the feasibility stage. The safety analysis covered the operations from the reception of the waste transport casks to the disposal of the waste disposal package in its final emplacement location inside the disposal cell. Since the surface facilities' operations are similar to those of other nuclear ones, this paper focuses on the specificity of the deep repository, i.e. the operational safety and radioprotection aspects applied to the deep disposal drift. Andra has selected an ILW-LL design based on large horizontal drifts (diameters of 10 to 12 m, and lengths of 250 m). The primary waste packages are put inside a specific concrete overpack before their disposal. These overpacks are remotely stacked inside the horizontal drifts. The operational safety analysis aims to ensure that risks are kept under control through provisions in the design of the repository and by operating the facility in compliance with operational requirements and the safety functions. The requirements and the safety functions, developed at this stage of the feasibility studies, will be explained. The operational safety analysis is structured around physical components and real activities (construction, operation, closure) through a dedicated risk analysis. Due to the large variety of different ILW-LL waste, in order to identify the potential

Considerations Related To Human Intrusion In The Context Of Disposal Of Radioactive Waste-The IAEA HIDRA Project

Energy Technology Data Exchange (ETDEWEB)

Seitz, Roger; Kumano, Yumiko; Bailey, Lucy; Markley, Chris; Andersson, Eva; Beuth, Thomas

2014-01-09

The principal approaches for management of radioactive waste are commonly termed ‘delay and decay’, ‘concentrate and contain’ and ‘dilute and disperse’. Containing the waste and isolating it from the human environment, by burying it, is considered to increase safety and is generally accepted as the preferred approach for managing radioactive waste. However, this approach results in concentrated sources of radioactive waste contained in one location, which can pose hazards should the facility be disrupted by human action in the future. The International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA), and Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) agree that some form of inadvertent human intrusion (HI) needs to be considered to address the potential consequences in the case of loss of institutional control and loss of memory of the disposal facility. Requirements are reflected in national regulations governing radioactive waste disposal. However, in practice, these requirements are often different from country to country, which is then reflected in the actual implementation of HI as part of a safety case. The IAEA project on HI in the context of Disposal of RadioActive waste (HIDRA) has been started to identify potential areas for improved consistency in consideration of HI. The expected outcome is to provide recommendations on how to address human actions in the safety case in the future, and how the safety case may be used to demonstrate robustness and optimize siting, design and waste acceptance criteria within the context of a safety case.

Considerations Related To Human Intrusion In The Context Of Disposal Of Radioactive Waste-The IAEA HIDRA Project

International Nuclear Information System (INIS)

Seitz, Roger; Kumano, Yumiko; Bailey, Lucy; Markley, Chris; Andersson, Eva; Beuth, Thomas

2014-01-01

The principal approaches for management of radioactive waste are commonly termed ''delay and decay'', ''concentrate and contain'' and ''dilute and disperse''. Containing the waste and isolating it from the human environment, by burying it, is considered to increase safety and is generally accepted as the preferred approach for managing radioactive waste. However, this approach results in concentrated sources of radioactive waste contained in one location, which can pose hazards should the facility be disrupted by human action in the future. The International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA), and Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) agree that some form of inadvertent human intrusion (HI) needs to be considered to address the potential consequences in the case of loss of institutional control and loss of memory of the disposal facility. Requirements are reflected in national regulations governing radioactive waste disposal. However, in practice, these requirements are often different from country to country, which is then reflected in the actual implementation of HI as part of a safety case. The IAEA project on HI in the context of Disposal of RadioActive waste (HIDRA) has been started to identify potential areas for improved consistency in consideration of HI. The expected outcome is to provide recommendations on how to address human actions in the safety case in the future, and how the safety case may be used to demonstrate robustness and optimize siting, design and waste acceptance criteria within the context of a safety case

Deep underground disposal of radioactive wastes: Near field effects

International Nuclear Information System (INIS)

1985-01-01

This report reviews the important near-field effects of the disposal of wastes in deep rock formations. The basic characteristics of waste form, container and package, buffer and backfill materials and potential host-rock types are discussed from the perspective of the performance requirements of the total repository system. Effects of waste emplacement on the separate system components and on the system as a whole are discussed. The effects include interactions between groundwater and brines and the other system components, thermal and thermo-mechanical effects, and chemical and geochemical reactions. Special consideration is given to the radiation field that exists in proximity to the waste containers and also to the coupled effects of different phenomena

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

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

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.

Non-technical issues in safety assessments for nuclear disposal facilities

International Nuclear Information System (INIS)

Kallenbach-Herbert, Beate; Brohmann, Bettina

2010-09-01

The paper highlights that a comprehensive approach to safety affords the consideration of technology, organisation, personnel and social environment. In several safety relevant contexts of nuclear waste disposal these fields are closely interrelated. The approach for the consideration of socio-scientific aspects which is sketched in this paper supports the systematic treatment of safety relevant non-technical issues in the safety case or in safety assessments for a disposal project. Furthermore it may foster the dialogue among specialists from the technical, the natural- and the socio-scientific field on questions of disposal safety. In this way it may contribute to a better understanding among the affected scientific disciplines in nuclear waste disposal.

Consideration of Criteria for a Conceptual Near Surface Radioactive Waste disposal Facility in Kenya

Energy Technology Data Exchange (ETDEWEB)

Nderitu, Stanley Werugia; Kim, Changlak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2014-05-15

The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures. This study will present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and illustrate some of its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in a conceptual near surface disposal facility in Kenya. The approach will make use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities. The study will mainly focus on post-closure periods. The study will employ some specific inadvertent human intrusion scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. The specific performance assessments will use modified scenarios and data to establish acceptable disposal concentrations for specific disposal sites and conditions. Safety and environmental impacts assessments is required in the post-closure phase to support particular decisions in development, operation, and closure of a near surface repository.

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)

Environmental monitoring considerations for low-level waste disposal sites

International Nuclear Information System (INIS)

Sedlet, J.

1982-01-01

All waste disposal sites are required to monitor the environment. The proposed NRC licensing rule, 10 CFR Part 61, requires that such monitoring be conducted before, during, and after a site is operated. An adequate monitoring program consists of measuring concentrations of radionuclides, chemically-toxic substances, and leachate indicators in environmental media and of evaluating specific physical properties of the site. In addition, the composition of the buried waste must be known. Methods for obtaining this information are discussed and monitoring programs are presented for the preoperational, operational, and postclosure phases of a disposal site. Environmental monitoring is considered in a broad context, since it includes monitoring burial trenches onsite, as well as surveillance in the offsite environment. Postclosure monitoring programs will be strongly influenced by the operational monitoring results. In some respects, this phase will be easier since the migration pathways should be well known and the number of radionuclides of concern reduced by radioactive decay. The results of the environmental monitoring program will be vital to successful site operation. These results should be used to determine if operational changes are needed and to predict future environmental impacts

Status of commercial nuclear high-level waste disposal. Special report

International Nuclear Information System (INIS)

Dau, G.J.; Williams, R.F.

1976-09-01

The results of this review, presented in the form of a functional description of high level waste management system, shows that technology is available to dispose of nuclear waste safely by several different processes. The most attractive alternative in terms of available technology and shortness of time to demonstrate it at commercial scale is a system that converts the waste to a solid by immobilizing the radioactive elements in a glass matrix. Brief comments are also given on international efforts in high level waste management and advanced disposal concepts

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.

Reduction requirements for actinides with special regard to the isolation time at final disposal

International Nuclear Information System (INIS)

Philippen, P.W.

1996-01-01

The additional knowledge acquired about the metabolism of the actinide elements, and the experience with the development of cancer risk have resulted in several realignments of the ALI limits by the ICRP. This needs a re-evaluation of the toxicity potential inherent in the nuclear fuel cycles of nuclear reactors and a re-evaluation of drawn conclusions. The radiotoxical evaluation of actinides and long-lived fission products are presented and discussed with special regard to Partitioning and Transmutation (P and T) issues. Detailed information about balancing the toxicity potential flow and its growth during the nuclear fuel cycle is given in order to determine a reference value for the comparison of natural and man-made toxicity. Calculations for different fuel types are exhibited and the resulting toxicity potentials are compared to these reference values in order to solely quantify in an idealized way the consequences of human action. The long-term toxicity potential of discharged PWR-fuels in case of direct disposal as well as Pu-recycling within MOX elements using U and Th are presented. The inherent drawbacks leads to the conclusion that with respect to a modified goal of final disposal only a full-scale P and T scheme is able to achieve long-term toxicity potentials on the same level as that of fresh fuel decaying naturally. Thus, the storage in a repository can relay more heavily on engineered barriers. (author). 15 refs, 9 figs, 1 tab

Disposal of mixed waste: Technical, institutional, and policy factors

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Letourneau, M.J.; Case, J.T.

1996-01-01

In conjunction with the affected States as part of their interactions required by the Federal Facilities Compliance Act, the Department of Energy has been developing a process for a disposal configuration for its mixed low-level waste (MLLW). This effort, spanning more than two years, has reduced the potential disposal sites from 49 to 15. The remaining 15 sites have been subjected to a performance evaluation to determine their strengths and weaknesses for disposal of MLLW. The process has included institutional and policy factors as well as strictly technical analyses, and technical analyses must be supported by technical analyses, and technical analyses must be performed within a framework which includes some institutional considerations, with the institutional considerations selected for inclusion largely a matter of policy. While the disposal configuration process is yet to be completed, the experience to date offers a viable approach for solving some of these issues. Additionally, several factors remain to be addressed before an MLLW disposal configuration can be developed

Potential co-disposal of greater-than-class C low-level radioactive waste with Department of Energy special case waste - greater-than-class C low-level waste management program

International Nuclear Information System (INIS)

Allred, W.E.

1994-09-01

This document evaluates the feasibility of co-disposing of greater-than-Class C low-level radioactive waste (GTCC LLW) with U.S. Department of Energy (DOE) special case waste (SCW). This document: (1) Discusses and evaluates key issues concerning co-disposal of GTCC LLW with SCW. This includes examining these issues in terms of regulatory concerns, technical feasibility, and economics; (2) Examines advantages and disadvantages of such co-disposal; and (3) Makes recommendations. Research and analysis of the issues presented in this report indicate that it would be technically and economically feasible to co-dispose of GTCC LLW with DOE SCW. However, a dilemma will likely arise in the current division of regulatory responsibilities between the U.S. Nuclear Regulatory Commission and DOE (i.e., current requirement for disposal of GTCC LLW in a facility licensed by the Nuclear Regulatory Commission). DOE SCW is currently not subject to this licensing requirement

Special Analysis: Revised 14C Disposal Limits for the Saltstone Disposal Facility

International Nuclear Information System (INIS)

Kaplan, D.I.

2004-01-01

The Saltstone Special Analysis calculated a limit for 14C based on the atmospheric pathway of 52 pCi/mL using some very conservative assumptions. This was compared to the estimated Low Curie Salt concentration of 0.45 pCi/mL and since the limit was two orders of magnitude greater than the estimated concentration, the decision was made that no further analysis was needed. The 14C concentration in Tank 41 has been found to be much greater than the estimated concentration and to exceed the limit derived in the Special Analysis. A rigorous analysis of the release of 14C via the air pathway that considers the chemical effects of the Saltstone system has shown that the flux of 14C is significantly less than that assumed in the Special Analysis. The net result is an inventory limit for 14C that is significantly higher than that derived in the Special Analysis that will also meet the performance objectives of DOE Order 435.1

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.

Removal of Legacy Low-Level Waste Reactor Moderator De-ionizer Resins Highly Contaminated with Carbon-14 from the 'Waste with no Path to Disposal List' Through Innovative Technical Analysis and Performance Assessment Techniques

International Nuclear Information System (INIS)

Goldston, W.T.; Hiergesell, R.A.; Kaplan, D.I.; Pope, H.L.

2006-01-01

At the Savannah River Site (SRS), nuclear production reactors used de-ionizers to control the chemistry of the reactor moderator during their operation to produce nuclear materials primarily for the weapons program. These de-ionizers were removed from the reactors and stored as a legacy waste and due to the relatively high carbon-14 (C-14) contamination (i.e., on the order of 740 giga becquerel (GBq) (20 curies) per de-ionizer) were considered a legacy 'waste with no path to disposal'. Considerable progress has been made in consideration of a disposal path for the legacy reactor de-ionizers. Presently, 48 - 50 de-ionizers being stored at SRS have 'no path to disposal' because the disposal limit for C-14 in the SRS's low-level waste disposal facility's Intermediate Level Vault (ILV) is only 160 GBq (4.2 curies) per vault. The current C-14 ILV disposal limit is based on a very conservative analysis of the air pathway. The paper will describe the alternatives that were investigated that resulted in the selection of a route to pursue. This paper will then describe SRS's efforts to reduce the conservatism in the analysis, which resulted in a significantly larger C-14 disposal limit. The work consisted of refining the gas-phase analysis to simulate the migration of C-14 from the waste to the ground surface and evaluated the efficacy of carbonate chemistry in cementitious environment of the ILV for suppressing the volatilization of C-14. During the past year, a Special Analysis was prepared for Department of Energy approval to incorporate the results of these activities that increased the C-14 disposal limits for the ILV, thus allowing for disposal of the Reactor Moderator De-ionizers. Once the Special Analysis is approved by DOE, the actual disposal would be dependent on priority and funding, but the de-ionizers will be removed from the 'waste with no path to disposal list'. (authors)

Institutional considerations for near-surface land disposal

International Nuclear Information System (INIS)

Gustafson, P.F.

1989-01-01

This chapter discusses the federal and state responsibilities for low level radioactive waste and the laws and policies that have been enacted to define those responsibilities. Historical perspective is given on the intent by both Congress and the Atomic Energy Commission to keep all nuclear activity other than regulating and licensing in the private sector. The Low Level Waste Policy Act of 1980 and the 1985 Amendments are described along with the ramifications for states. Individual state approaches and regional compacts for LLW management are examined and the following general issues common to all endeavors are considered: Public involvement, Management plans, Economic viability, Site selection criteria, Site acceptance incentives, Disposal technology, Selection of site operator, and Site ownership. Finally, licensing and other regulatory responsibilities; site closure, long-term ownership, and fiscal responsibility; unresolved issues; and flaws in the present compact alignments are discussed

Regional disposal, a feasible solution for Romania

International Nuclear Information System (INIS)

Radu, Maria

2004-01-01

Almost every country that exploits or builds nuclear power plants is engaged in its own research or international cooperation programs aiming at identification of optimal solutions of closing the fuel cycle and finding feasible technologies for final disposal of spent fuel and high-level wastes resulting from reprocessing. The general trend that manifests in these countries is to manage on their own territories the final disposal while considering the possibility of regional arrangements for common disposal. But this latter alternative has not been definitively analyzed and decided upon. Hence, European Union and IAEA look for solutions of long term (of the order of hundreds years) for the final disposal, particularly within regional facilities. Multinational repositories where disposal of high-level wastes or spent fuel should appear as a paid specialized servicing, where the operation technical conditions would be well established, as secure from nuclear safety and physical point of view, under the provisions of safeguards agreements, are still under consideration. No matter of the option which will be chosen, closing the nuclear cycle and ensuring a final disposal facility for radioactive wastes are compulsory tasks and issues with many aspects in common (establishing a site hosted by stable deep geological formations, protection by engineered barriers to prevent dispersion of radioactive products into the environment, long term analyses, etc). In this circumstances, having in mind that no other variant appears to be achievable before 2020-2050, intermediate term storage appears as compulsory a solution in developing the fuel cycle both world wide and in Romania, As early as in the first half of 2003 at Cernavoda, the Intermediate Storage for Spent Fuel (DICA) was commissioned. This is a facility founded for the first time in Romania aiming at closing the fuel cycle. The paper presents the current issues and the results obtained so far within the frame of

The ethics in qualitative health research: special considerations.

Science.gov (United States)

Peter, Elizabeth

2015-09-01

A sound knowledge of the nature of qualitative research, along with an appreciation of some special ethical considerations, is needed for rigorous reviews to be conducted. The overall character of qualitative research is described with an emphasis on the tendency of qualitative researchers to explore sensitive topics using theoretically informed methods. A number of specific features of qualitative that require additional ethical attention and awareness are also examined including the following: 1) participants are frequently quite vulnerable and require protection because the data collection methods, such as in-depth interviews, can delve into personally and politically charged matters; 2) naturalistic observation can raise concerns regarding privacy and consent; 3) the potential for the identifiability of the results of this research may require extra efforts to maintain confidentiality. Ultimately, Reseach Ethics Committee members must be knowledgeable about qualitative approaches to be able to assess the potential harms and benefits in a protocol carefully. Without this knowledge gaining ethics approval can be overly difficult for researchers and the best practices for protecting human participants can be overlooked.

The ethics in qualitative health research: special considerations

Directory of Open Access Journals (Sweden)

Elizabeth Peter

2015-09-01

Full Text Available Abstract A sound knowledge of the nature of qualitative research, along with an appreciation of some special ethical considerations, is needed for rigorous reviews to be conducted. The overall character of qualitative research is described with an emphasis on the tendency of qualitative researchers to explore sensitive topics using theoretically informed methods. A number of specific features of qualitative that require additional ethical attention and awareness are also examined including the following: 1 participants are frequently quite vulnerable and require protection because the data collection methods, such as in-depth interviews, can delve into personally and politically charged matters; 2 naturalistic observation can raise concerns regarding privacy and consent; 3 the potential for the identifiability of the results of this research may require extra efforts to maintain confidentiality. Ultimately, Reseach Ethics Committee members must be knowledgeable about qualitative approaches to be able to assess the potential harms and benefits in a protocol carefully. Without this knowledge gaining ethics approval can be overly difficult for researchers and the best practices for protecting human participants can be overlooked.

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

Seabed Disposal Program. Annual report, January--December 1975

International Nuclear Information System (INIS)

Talbert, D.M.

1976-05-01

This document is the report of the activities in the Seabed Disposal Program for CY 1975. A summary is given of the progress made to determine the feasibility of disposal of high-level solidified and encapsulated radioactive wastes into the deep seafloor. While a considerable amount of work remains to be done to assure safety and feasibility, no technological reasons have been presented that would preclude the possibility of successful disposal into submarine geologic media

Engineering, environmental and economic planning for tailings disposal

International Nuclear Information System (INIS)

Poellot, J.H.

1982-01-01

There are two principal points made in this paper. First, mining waste materials, or tailings, are geotechnical materials. Their behavior follows the principles of soil mechanics and is predictable by these principles. Second, proper disposal, meaning safe, environmentally sound and economical disposal, requires planning and recognizing waste disposal as part of the total mining system and process. In the development of these two principles, planning, design, and economic considerations of mine tailings are discussed

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)

Evaluation of a disposable plastic Neubauer counting chamber for semen analysis.

Science.gov (United States)

Kirkman-Brown, Jackson; Björndahl, Lars

2009-02-01

To evaluate whether disposable plastic counting chambers effectively could replace nondisposable, time-consuming, and potentially dangerous glass hemocytometers. Evaluation of equipment in modern laboratory andrology. Comparison of results obtained with plastic chambers with results obtained with "gold-standard" glass hemocytometer counts. Diagnostic laboratory for andrology. Twenty-one patients undergoing investigation for infertility problems. No interventions with patients; sperm in diluted semen samples were used when patients had allowed the use for research and training. Sperm concentration, difference from results obtained with standard equipment. In the first three experimental series, with use of standard routine phase-contrast microscopy, significantly lower count results were obtained consistently from the plastic chambers than from standard chambers. In the fourth series, with use of specialized equipment, equivalent results were obtained but with a considerably greater time commitment because of difficulties in distinguishing sperm adjacent to the gridlines in the plastic chambers. The plastic disposable chamber type was not suitable for routine semen analysis because results are variable depending on the microscope used, and increased time is necessary to do the assessment accurately.

Integrating ethical and technical considerations in the energy debate

International Nuclear Information System (INIS)

Pickering, G.W.

1980-01-01

A study being carried out by the author on analyzing and integrating ethical and technical considerations in formulating an energy policy for the United States, with special emphasis on nuclear issues, is reviewed. Beginning with an overview of the historical development of the American nuclear program and the emergence of an organized politcal opposition to that program, seven outstanding issues are identified: institutional adequacy, radiation, reactor safety, waste disposal, economics and reliability, international consequences, and alternative energy sources, and an attempt is made to identify the range of dispute in relation to each. A framework is proposed for analyzing these issues by introducing guidelines for defining a social justice problem. Suggestions are made about how to get morally serious about such issues, and this framework is applied to four issues: radiation, reactor safety, waste disposal, and institutional adequacy. Ultimately it is a political choice whether or not to include nuclear power in a nations's energy policy. It is important, however, that such choices be made using the best technical and ethical assessments of the consequences. (LL)

De minimis concepts in radioactive waste disposal. Considerations in defining de minimis quantities of solid radioactive waste for uncontrolled disposal by incineration and landfill

International Nuclear Information System (INIS)

1983-02-01

This document deals with recommendations addressed to those national authorities wishing to dispose of low level radioactive waste into the terrestrial environment, on how de minimis levels or quantities can be derived. The only radioactive materials covered here are declared solid radioactive wastes of very low activity which are controlled up to the point where deliberate control is lost, or wastes below a level that requires regulatory control. As regards the disposal sites, these wastes are not intended to be disposed of in fully controlled disposal facilities, such as repositories located in shallow land, rock cavities, etc. On the other hand, it is considered that these materials should not be disposed of in any place, but should be handled like other municipal wastes. Among the different techniques available, only two are considered in this document, namely a sanitary landfill facility, and an urban incineration plant

Packaging, Transportation, and Disposal Logistics for Large Radioactively Contaminated Reactor Decommissioning Components

International Nuclear Information System (INIS)

Lewis, Mark S.

2008-01-01

The packaging, transportation and disposal of large, retired reactor components from operating or decommissioning nuclear plants pose unique challenges from a technical as well as regulatory compliance standpoint. In addition to the routine considerations associated with any radioactive waste disposition activity, such as characterization, ALARA, and manifesting, the technical challenges for large radioactively contaminated components, such as access, segmentation, removal, packaging, rigging, lifting, mode of transportation, conveyance compatibility, and load securing require significant planning and execution. In addition, the current regulatory framework, domestically in Titles 49 and 10 and internationally in TS-R-1, does not lend itself to the transport of these large radioactively contaminated components, such as reactor vessels, steam generators, reactor pressure vessel heads, and pressurizers, without application for a special permit or arrangement. This paper addresses the methods of overcoming the technical and regulatory challenges. The challenges and disposition decisions do differ during decommissioning versus component replacement during an outage at an operating plant. During decommissioning, there is less concern about critical path for restart and more concern about volume reduction and waste minimization. Segmentation on-site is an available option during decommissioning, since labor and equipment will be readily available and decontamination activities are routine. The reactor building removal path is also of less concern and there are more rigging/lifting options available. Radionuclide assessment is necessary for transportation and disposal characterization. Characterization will dictate the packaging methodology, transportation mode, need for intermediate processing, and the disposal location or availability. Characterization will also assist in determining if the large component can be transported in full compliance with the transportation

Safety considerations of disposal of disused sealed sources in Puspokszilagy Repository, Hungary

International Nuclear Information System (INIS)

2003-01-01

The report presents the management of radioactive waste in Hungary Puspokszilagy Repository (RWTDF) including waste acceptance criteria, safety assessments, Action Plan for the safety improvement and present projects. The Puspokszilagy Repository is a typical near-surface repository, sink into the ground 6 m depth. The facility is a shallow land disposal type, appropriated for disposal of short and medium lived LILW, acceptable for temporary storage of long lived LILW. It consists of vaults containing cells for solidified drummed waste, wells for spent sealed sources, work building for treatment and interim storage and office building for environmental measurements. Two safety assessments have been performed in 2000 and 2002. The new safety assessment confirms the main statements of SA 2000, according to which several waste types can cause serious problems in the distant future: Until the finish of passive control the safety of the environment is guaranteed. After that time it is possible to arise events leading to exceeding of dose restricts (more then 10 mSv/yr but less then 100 mSv/yr), because of disposal of long lived radionuclides (mainly C-14,Tc-99, Ra-226, Th-232, U-234) and significant activities of Cs-137 sources.There are uncertainties in radionuclide amounts and distributions, as well as in the physical and chemical characteristics of the wastes that determine radionuclide mobility and toxicity. The recommendations to improve the safety include: Long lived SSRS in the 'B' and 'D' wells should be removed before the closure of repository. Large Cs-137 sources and long lived sources in the 'A' vaults should be recovered (if its feasible); All vaults should be backfilled to provide chemical conditioning; The waste packaged in plastic bags should be repackaged and compacted into drums or containers; The inventory should be revise. Waste acceptance requirements in the future are: The disposal of long lived radionuclides is no permitted. The long lived waste

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)

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

Disposal of low- and intermediate-level solid radioactive wastes in rock cavities

International Nuclear Information System (INIS)

1983-01-01

This Guidebook summarizes the factors to be considered and the activities to be undertaken in the overall planning and development of a disposal system for solid or solidified low- and intermediate-level wastes in rock cavities. Aspects related to repository site selection, design, construction, operation, shutdown, surveillance, regulation and safety assessment are discussed here in general terms. They will be covered in greater technical detail in a separate document. This report considers the emplacement of wastes in categories II, III, IV and V, as defined in Table 3.1, in different kinds of cavities located at various depths from just below the surface to deep continental rock. The choice of the type of cavity and its depth and of the disposal site itself is related to the radiological protection requirements for the wastes concerned. The repositories considered include natural caves and abandoned mines as well as specially excavated cavities in various geological formations. Consideration is also given to hydrogeological, environmental and societal factors. The guidelines given in the report are made sufficiently general to cover a broad variety of different circumstances. Consequently, the practical application of these guidelines needs a case-by-case consideration which takes into account the local conditions, e.g. natural circumstances, the characteristics of the wastes and national and international regulations and practices

The disposal of radioactive wastes in Brazil with special emphasis on rocks

International Nuclear Information System (INIS)

Enokihara, Cyro Teiti

1983-01-01

The disposal of radioactive wastes in geological formations seems to be the most appropriate solution for the nuclear waste problem. The disposal sites must provide the maximum safety for the radionuclides during its decay period. The study presents a general analysis of three types rocks: salt, granite and basalt. In our analysis we have dealt with the following aspects: geology, tectonics, seismicity, hydrogeology , mineral resources, geomorphology, population and access. The studied regions were: Sergipe-Alagoas and Reconcavo Basins, Northeastern and Southeastern Folded Regions and Parana Basin. Our study contains the macro-analysis needed for the selection of a safe site for radioactive waste disposal. We believe this work will be useful as a first step for further micro-analysis of selected sites. (author)

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

Application of geographical information system in disposal site selection for hazardous wastes.

Science.gov (United States)

Rezaeimahmoudi, Mehdi; Esmaeli, Abdolreza; Gharegozlu, Alireza; Shabanian, Hassan; Rokni, Ladan

2014-01-01

The aim of this study was to provide a scientific method based on Geographical Information System (GIS) regarding all sustainable development measures to locate a proper landfill for disposal of hazardous wastes, especially industrial (radioactive) wastes. Seven effective factors for determining hazardous waste landfill were applied in Qom Province, central Iran. These criteria included water, slope, population centers, roads, fault, protected areas and geology. The Analysis Hierarchical Process (AHP) model based on pair comparison was used. First, the weight of each factor was determined by experts; afterwards each layer of maps entered to ARC GIS and with special weight multiplied together, finally the best suitable site was introduced. The most suitable sites for burial were in northwest and west of Qom Province and eventually five zones were introduced as the sample sites. GIs and AHP model is introduced as the technical, useful and accelerator tool for disposal site selection. Furthermore it is determined that geological factor is the most effective layer for site selection. It is suggested that geological conditions should be considered primarily then other factors are taken into consideration.

Safety considerations of disposal of disused sealed sources in near surface facilities

International Nuclear Information System (INIS)

Pla, E.

2003-01-01

The report presents European commission studies on sealed radioactive sources - Management of Spent Radiation Sources in the European Union: Quantities, Storage, Recycling and Disposal. EUR 16960 EN. EC 1996; Management of sealed radioactive sources produced and sold in the Russian Federation. EUR 18191 EN. EC, 1999; Management and Disposal of Disused Sealed Radioactive Sources in the European Union. EUR 18186 EN. EC, 2000; Management of Spent Sealed Radioactive Sources in Central and Eastern Europe. EUR 19842 EN. EC, April 2001; Management of Spent Sealed Radioactive Sources in Bulgaria, Latvia, Lithuania, Romania and Slovakia. EUR 20654 EN. EC, January 2003. The conclusions and recommendations in them are given. The International catalogue of sealed radioactive sources and devices is described

German concept and status of the disposal of spent fuel elements from German research reactors

International Nuclear Information System (INIS)

Komorowski, K.; Storch, S.; Thamm, G.

1995-01-01

Eight research reactors with a power ≥ 100 kW are currently being operated in the Federal Republic of Germany. These comprise three TRIGA-type reactors (power 100 kW to 250 kW), four swimming-pool reactors (power 1 MW to 10 MW) and one DIDO type reactor (power 23 MW). The German research reactors are used for neutron scattering for basic research in the field of solid state research, neutron metrology, for the fabrication of isotopes and for neutron activation analysis for medicine and biology, for investigating the influence of radiation on materials and for nuclear fuel behavior. It will be vital to continue current investigations in the future. Further operation of the German research reactors is therefore indispensable. Safe, regular disposal of the irradiated fuel elements arising now and in future operation is of primary importance. Furthermore, there are several plants with considerable quantities of spent fuel, the safe disposal of which is a matter of urgency. These include above all the VKTA facilities in Rossendorf and also the TRIGA reactors, where disposal will only be necessary upon decommissioning. The present paper report is concerned with the disposal of fuel from the German research reactors. It briefly deals with the situation in the USA since the end of 1988, describes interim solutions for current disposal requirements and then mainly concentrates on the German disposal concept currently being prepared. This concept initially envisages the long-term (25--50 years) dry interim storage of fuel elements in special containers in a central German interim store with subsequent direct final disposal without reprocessing of the irradiated fuel

[Do Current German-Language Intelligence Tests Take into Consideration the Special Needs of Children with Disabilities?].

Science.gov (United States)

Mickley, Manfred; Renner, Gerolf

2015-01-01

Do Current German-Language Intelligence Tests Take into Consideration the Special Needs of Children with Disabilities? A review of 23 German intelligence test manuals shows that test-authors do not exclude the use of their tests for children with disabilities. However, these special groups play a minor role in the construction, standardization, and validation of intelligence tests. There is no sufficient discussion and reflection concerning the issue which construct-irrelevant requirements may reduce the validity of the test or which individual test-adaptations are allowed or recommended. Intelligence testing of children with disabilities needs more empirical evidence on objectivity, reliability, and validity of the assessment-procedures employed. Future test construction and validation should systematically analyze construct-irrelevant variance in item format, the special needs of handicapped children, and should give hints for useful test-adaptations.

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

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.

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

Using performance assessment for radioactive waste disposal decision making -- implementation of the methodology into the third performance assessment iteration of the Greater Confinement Disposal site

International Nuclear Information System (INIS)

Gallegos, D.P.; Conrad, S.H.; Baer, T.A.

1993-01-01

The US Department of Energy is responsible for the disposal of a variety of radioactive wastes. Some of these wastes are prohibited from shallow land burial and also do not meet the waste acceptance criteria for proposed waste repositories at the Waste Isolation Pilot Plant (WIPP) and Yucca Mountain. These have been termed ''special-case'' waste and require an alternative disposal method. From 1984 to 1989, the Department of Energy disposed of a small quantity of special-case transuranic wastes at the Greater Confinement Disposal (GCD) site at the Nevada Test Site. In this paper, an iterative performance assessment is demonstrated as a useful decision making tool in the overall compliance assessment process for waste disposal. The GCD site has been used as the real-site implementation and test of the performance assessment approach. Through the first two performance assessment iterations for the GCD site, and the transition into the third, we demonstrate how the performance assessment methodology uses probabilistic risk concepts to guide affective decisions about site characterization activities and how it can be used as a powerful tool in bringing compliance decisions to closure

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

USEPA consideration of human intrusion in setting radioactive waste disposal standards

International Nuclear Information System (INIS)

Egan, D.J.; Hadlock, C.R.

1989-01-01

In 1985, the United States Environmental Protection Agency (USEPA) promulgated standards for the disposal of spent nuclear fuel and high-level and transuranic radioactive wastes (40 CFR Part 191). These standards placed limits, called containment requirements, on the projected releases of radioactivity due to both normal and accidental events for 10,000 years after disposal. The standards also contained qualitative assurance requirements that described the role foreseen for both active and passive institutional controls. They included both requirements for such institutional controls and limitations on the ways that they could be relied upon. This paper describes these assumptions about institutional controls made by the USEPA, and it discusses the types of future societies that would be consistent with such assumptions. The paper also reviews the USEPA's approach towards assessing the long-term performance of mined geologic repositories. In these assessments, the risks caused by inadvertent human intrusion into the area of a repository usually dominate the risks projected from other release scenarios. The assumptions made about inadvertent intrusion are discussed, and they are related to the policies regarding institutional controls. The disposal standards that the USEPA promulgated in 1985 were overturned by a Federal court in 1987, and the Agency is now preparing revised standards for public review and comment. These are expected to by published in 1990. However, the approaches regarding institutional controls and human intrusion are expected to remain the same as those used in 1985. Some paragraphs (selected by the NEA Secretariat) of 40 CFR Part 191, subpart B (as of 1985 version) with particular relevance to human intrusion are cited

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

Low-level radioactive waste disposal in the USA - Use of mill tailings impoundments as a new policy option

International Nuclear Information System (INIS)

Farrell, C.W.

2006-01-01

Disposal of low-level radioactive waste (LLW) in the United States is facing severe and immediate capacity limitations. Seemingly intractable regulatory and jurisdictional conflicts make establishment of new LLW disposal sites effectively impossible. Uranium mill tailings impoundments constructed at conventional uranium open-cast and underground mines could offer approximately 40 to 80+ million tons of disposal capacity for low activity radioactive waste. Such impoundments would provide an enhanced, high level of environmental and health and safety protection for the direct disposal of depleted uranium, special nuclear material, technologically-enhanced, naturally-occurring radioactive material (TENORM) and mixed waste. Many waste streams, such as TENORM and decommissioning rubble, will be high-volume, low activity materials and ideally suited for disposal in such structures. Materials in a given decay chain with a total activity from all radionuclides present of ∼820 Bq/g (2.22 x 10 -08 Ci/g) with no single radionuclide present in an activity greater than ∼104 Bq/g (2,800 pCi/g) should be acceptable for disposal. Materials of this type could be accepted without any site-specific dose modelling, so long as the total activity of the tailings impoundment not exceed its design capacity (generally 82 x 10 07 Bq/metric tonne) (0.020 Ci/short ton) and the cover design requirements to limit radon releases are satisfied. This paper provides background on US LLW disposal regulations, examines LLW disposal options under active consideration by the US Environmental Protection Agency and Department of Energy, develops generic waste acceptance criteria and identifies policy needs for federal and state governments to facilitate use of uranium mill tailings impoundments for LLW disposal. (author)

Methods of characterization of salt formations in view of spent fuel final disposal

International Nuclear Information System (INIS)

Diaconu, Daniela; Balan, Valeriu; Mirion, Ilie

2002-01-01

Deep disposal in geological formations of salt, granite and clay seems to be at present the most proper and commonly adopted solution for final disposal of high-level radioactive wastes and spent fuel. Disposing such wastes represents the top-priority issue of the European research community in the field of nuclear power. Although seemingly premature for Romanian power system, the interest for final disposal of spent fuel is justified by the long duration implied by the studies targeting this objective. At the same time these studies represent the Romanian nuclear research contribution in the frame of the efforts of integration within the European research field. Although Romania has not made so far a decision favoring a given geological formation for the final disposal of spent fuel resulting from Cernavoda NPP, the most generally taken into consideration appears the salt formation. The final decision will be made following the evaluation of its performances to spent fuel disposal based on the values of the specific parameters of the geological formation. In order to supply the data required as input parameters in the codes of evaluation of the geological formation performances, the INR Pitesti initiated a package of modern and complex methodologies for such determinations. The studies developed so far followed up the special phenomenon of salt convergence, a phenomenon characteristic for only this kind of rock, as well as the radionuclide migration. These studies allow a better understanding of these processes of upmost importance for disposal's safety. The methods and the experimental installation designed and realized at INR Pitesti aimed at determination of thermal expansion coefficient, thermal conductivity, specific heat, which are all parameters of high specific interest for high level radioactive waste or spent fuel disposal. The paper presents the results of these studies as well as the methodologies, the experimental installations and the findings

Co-disposal of mixed waste materials

International Nuclear Information System (INIS)

Phillips, S.J.; Alexander, R.G.; Crane, P.J.; England, J.L.; Kemp, C.J.; Stewart, W.E.

1993-08-01

Co-disposal of process waste streams with hazardous and radioactive materials in landfills results in large, use-efficiencies waste minimization and considerable cost savings. Wasterock, produced from nuclear and chemical process waste streams, is segregated, treated, tested to ensure regulatory compliance, and then is placed in mixed waste landfills, burial trenches, or existing environmental restoration sites. Large geotechnical unit operations are used to pretreat, stabilize, transport, and emplace wasterock into landfill or equivalent subsurface structures. Prototype system components currently are being developed for demonstration of co-disposal

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.

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

Nuclear waste and a deep geological disposal facility

International Nuclear Information System (INIS)

Vokal, A.; Laciok, A.; Vasa, I.

2005-01-01

The paper presents a systematic analysis of the individual areas of research into nuclear waste and deep geological disposal with emphasis on the contribution of Nuclear Research Institute Rez plc to such efforts within international projects, specifically the EURATOM 6th Framework Programme. Research in the area of new advanced fuel cycles with focus on waste minimisation is based on EU's REDIMPACT project. The individual fuel cycles, which are currently studied within the EU, are briefly described. Special attention is paid to fast breeders and accelerator-driven reactor concepts associated with new spent fuel reprocessing technologies. Results obtained so far show that none even of the most advanced fuel cycles, currently under consideration, would eliminate the necessity to have a deep geological repository for a safe storage of residual radioactive waste. As regards deep geological repository barriers, the fact is highlighted that the safety of a repository is assured by complementary engineered and natural barriers. In order to demonstrate the safety of a repository, a deep insight must be gained into any and all of the individual processes that occur inside the repository and thus may affect radioactivity releases beyond the repository boundaries. The final section of the paper describes methods of radioactive waste conditioning for its disposal in a repository. Research into waste matrices used for radionuclide immobilisation is also highlighted. (author)

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Complementary considerations 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

Complementary Considerations sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective of enhancing confidence in the outcomes of the safety assessment for a spent nuclear fuel repository to be constructed at Olkiluoto, Finland. The main emphasis in this report is on the evidence and understanding that can be gained from observations at the site, including its regional geological environment, and from natural and anthropogenic analogues for the repository, its components and the processes that affect safety. In particular, the report addresses diverse and less quantifiable types of evidence and arguments that are enclosed to enhance confidence in the outcome of the safety assessment. These complementary considerations have been described as evaluations, evidence and qualitative supporting arguments that lie outside the scope of the other reports of the quantitative safety assessment. The experience with natural analogues for the long-term durability of the materials involved and the extent of processes provides high confidence in our understanding of the disposal system and its evolution. For each engineered barrier and key process, there is increasing analogue evidence to support the conceptual models and parameters. Regarding the suitability of the Olkiluoto site to host a spent fuel repository, a number of factors have been identified that indicate the suitability of crystalline host rock in general, and that of the Olkiluoto site in particular. The report also provides radiation background information for the use of complementary indicators, which aid in putting the results of the safety analysis presented in Assessment of Radionuclide Release Scenarios for the Repository System and Biosphere Assessment in a broader perspective to show that the radiation originating from a spent nuclear fuel repository remains in most cases much below natural background radiation or that caused by non-nuclear industries. (orig.)

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Complementary considerations 2012

International Nuclear Information System (INIS)

2012-12-01

Complementary Considerations sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective of enhancing confidence in the outcomes of the safety assessment for a spent nuclear fuel repository to be constructed at Olkiluoto, Finland. The main emphasis in this report is on the evidence and understanding that can be gained from observations at the site, including its regional geological environment, and from natural and anthropogenic analogues for the repository, its components and the processes that affect safety. In particular, the report addresses diverse and less quantifiable types of evidence and arguments that are enclosed to enhance confidence in the outcome of the safety assessment. These complementary considerations have been described as evaluations, evidence and qualitative supporting arguments that lie outside the scope of the other reports of the quantitative safety assessment. The experience with natural analogues for the long-term durability of the materials involved and the extent of processes provides high confidence in our understanding of the disposal system and its evolution. For each engineered barrier and key process, there is increasing analogue evidence to support the conceptual models and parameters. Regarding the suitability of the Olkiluoto site to host a spent fuel repository, a number of factors have been identified that indicate the suitability of crystalline host rock in general, and that of the Olkiluoto site in particular. The report also provides radiation background information for the use of complementary indicators, which aid in putting the results of the safety analysis presented in Assessment of Radionuclide Release Scenarios for the Repository System and Biosphere Assessment in a broader perspective to show that the radiation originating from a spent nuclear fuel repository remains in most cases much below natural background radiation or that caused by non-nuclear industries. (orig.)

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Complementary considerations 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

Complementary Considerations sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective of enhancing confidence in the outcomes of the safety assessment for a spent nuclear fuel repository to be constructed at Olkiluoto, Finland. The main emphasis in this report is on the evidence and understanding that can be gained from observations at the site, including its regional geological environment, and from natural and anthropogenic analogues for the repository, its components and the processes that affect safety. In particular, the report addresses diverse and less quantifiable types of evidence and arguments that are enclosed to enhance confidence in the outcome of the safety assessment. These complementary considerations have been described as evaluations, evidence and qualitative supporting arguments that lie outside the scope of the other reports of the quantitative safety assessment. The experience with natural analogues for the long-term durability of the materials involved and the extent of processes provides high confidence in our understanding of the disposal system and its evolution. For each engineered barrier and key process, there is increasing analogue evidence to support the conceptual models and parameters. Regarding the suitability of the Olkiluoto site to host a spent fuel repository, a number of factors have been identified that indicate the suitability of crystalline host rock in general, and that of the Olkiluoto site in particular. The report also provides radiation background information for the use of complementary indicators, which aid in putting the results of the safety analysis presented in Assessment of Radionuclide Release Scenarios for the Repository System and Biosphere Assessment in a broader perspective to show that the radiation originating from a spent nuclear fuel repository remains in most cases much below natural background radiation or that caused by non-nuclear industries. (orig.)

Special Analysis for the Disposal of the Materials and Energy Corporation Sealed Sources at the Area 5 Radioactive Waste Management Site

Energy Technology Data Exchange (ETDEWEB)

Shott, Gregory [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

2017-05-15

This special analysis (SA) evaluates whether the Materials and Energy Corporation (M&EC) Sealed Source waste stream (PERM000000036, Revision 0) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the M&EC Sealed Source waste meets all U.S. Department of Energy (DOE) Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives (DOE 1999). The M&EC Sealed Source waste stream is recommended for acceptance without conditions.

Characteristics of low-level radioactive waste disposed during 1987--1989

International Nuclear Information System (INIS)

Roles, G.W.

1990-12-01

This report presents the volume, activity, and radionuclide distributions in low-level radioactive waste (LLW) disposed during 1987 through 1989 at the commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. The report has been entirely assembled from descriptions of waste provided in LLW shipment manifests. Individual radionuclide distributions are listed as a function of waste class, of general industry, and of waste stream. In addition, information is presented about disposal of wastes containing chelating agents, about use of solidification media, about the distribution of radiation levels at the surfaces of waste containers, and about the distribution of waste container sizes. Considerably more information is presented about waste disposed at the Richland and Beatty disposal facilities than at the Barnwell disposal facility

Tectonic and climatic considerations for deep geological disposal of radioactive waste: A UK perspective

International Nuclear Information System (INIS)

McEvoy, F.M.; Schofield, D.I.; Shaw, R.P.; Norris, S.

2016-01-01

Identifying and evaluating the factors that might impact on the long-term integrity of a deep Geological Disposal Facility (GDF) and its surrounding geological and surface environment is central to developing a safety case for underground disposal of radioactive waste. The geological environment should be relatively stable and its behaviour adequately predictable so that scientifically sound evaluations of the long-term radiological safety of a GDF can be made. In considering this, it is necessary to take into account natural processes that could affect a GDF or modify its geological environment up to 1 million years into the future. Key processes considered in this paper include those which result from plate tectonics, such as seismicity and volcanism, as well as climate-related processes, such as erosion, uplift and the effects of glaciation. Understanding the inherent variability of process rates, critical thresholds and likely potential influence of unpredictable perturbations represent significant challenges to predicting the natural environment. From a plate-tectonic perspective, a one million year time frame represents a very short segment of geological time and is largely below the current resolution of observation of past processes. Similarly, predicting climate system evolution on such time-scales, particularly beyond 200 ka AP is highly uncertain, relying on estimating the extremes within which climate and related processes may vary with reasonable confidence. The paper highlights some of the challenges facing a deep geological disposal program in the UK to review understanding of the natural changes that may affect siting and design of a GDF. - Highlights: • Natural processes are key to developing a safety case for geological disposal. • Key factors include plate tectonic and climate-mediated processes. • Process variability is a challenge to predicting the natural environment. • We highlight the challenges for geological disposal programs using

Tectonic and climatic considerations for deep geological disposal of radioactive waste: A UK perspective

Energy Technology Data Exchange (ETDEWEB)

McEvoy, F.M., E-mail: fmcevoy@bgs.ac.uk [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Schofield, D.I. [British Geological Survey, Tongwynlais, CF15 7NE (United Kingdom); Shaw, R.P. [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Norris, S. [Radioactive Waste Management Limited, B587, Curie Avenue, Harwell, Didcot OX11 0RH (United Kingdom)

2016-11-15

Identifying and evaluating the factors that might impact on the long-term integrity of a deep Geological Disposal Facility (GDF) and its surrounding geological and surface environment is central to developing a safety case for underground disposal of radioactive waste. The geological environment should be relatively stable and its behaviour adequately predictable so that scientifically sound evaluations of the long-term radiological safety of a GDF can be made. In considering this, it is necessary to take into account natural processes that could affect a GDF or modify its geological environment up to 1 million years into the future. Key processes considered in this paper include those which result from plate tectonics, such as seismicity and volcanism, as well as climate-related processes, such as erosion, uplift and the effects of glaciation. Understanding the inherent variability of process rates, critical thresholds and likely potential influence of unpredictable perturbations represent significant challenges to predicting the natural environment. From a plate-tectonic perspective, a one million year time frame represents a very short segment of geological time and is largely below the current resolution of observation of past processes. Similarly, predicting climate system evolution on such time-scales, particularly beyond 200 ka AP is highly uncertain, relying on estimating the extremes within which climate and related processes may vary with reasonable confidence. The paper highlights some of the challenges facing a deep geological disposal program in the UK to review understanding of the natural changes that may affect siting and design of a GDF. - Highlights: • Natural processes are key to developing a safety case for geological disposal. • Key factors include plate tectonic and climate-mediated processes. • Process variability is a challenge to predicting the natural environment. • We highlight the challenges for geological disposal programs using

Regional waste treatment with monolith disposal for low-level radioactive waste

International Nuclear Information System (INIS)

Forsberg, C.W.

1983-01-01

An alternative system is proposed for the disposal of low-level radioactive waste. This system, called REgional Treatment with MOnolith Disposal (RETMOD), is based on integrating three commercial technologies: automated package warehousing, whole-barrel rotary kiln incineration, and cement-based grouts for radioactive waste disposal. In the simplified flowsheet, all the sludges, liquids, resins, and combustible wastes are transported to regional facilities where they are incinerated. The ash is then mixed with special cement-based grouts, and the resulting mixture is poured into trenches to form large waste-cement monoliths. Wastes that do not require treatment, such as damaged and discarded equipment, are prepositioned in the trenches with the waste-cement mixture poured on top. The RETMOD system may provide higher safety margins by conversion of wastes into a solidified low-leach form, creation of low-surface area waste-cement monoliths, and centralization of waste processing into a few specialized facilities. Institutional problems would be simplified by placing total responsibility for safe disposal on the disposal site operator. Lower costs may be realized through reduced handling costs, the economics of scale, simplified operations, and less restrictive waste packaging requirements

Disposal of low- and intermediate-level solid radioactive wastes in rock cavities. A guidebook

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

This Guidebook summarizes the factors to be considered and the activities to be undertaken in the overall planning and development of a disposal system for solid or solidified low- and intermediate-level wastes in rock cavities. Aspects related to repository site selection, design, construction, operation, shutdown, surveillance, regulation and safety assessment are discussed here in general terms. They will be covered in greater technical detail in a separate document. This report considers the emplacement of wastes in categories II, III, IV and V, as defined in Table 3.1, in different kinds of cavities located at various depths from just below the surface to deep continental rock. The choice of the type of cavity and its depth and of the disposal site itself is related to the radiological protection requirements for the wastes concerned. The repositories considered include natural caves and abandoned mines as well as specially excavated cavities in various geological formations. Consideration is also given to hydrogeological, environmental and societal factors. The guidelines given in the report are made sufficiently general to cover a broad variety of different circumstances. Consequently, the practical application of these guidelines needs a case-by-case consideration which takes into account the local conditions, e.g. natural circumstances, the characteristics of the wastes and national and international regulations and practices.

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

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

Proceedings of the 1996 international conference on deep geological disposal of radioactive waste

International Nuclear Information System (INIS)

1996-01-01

The 1996 September International Conference on Deep Geological Disposal of Radioactive Waste was held in Winnipeg, Canada. Speakers from many countries that have or are developing geological disposal technologies presented the current research and implementation strategies for the deep geological disposal of radioactive wastes. Special sessions focused on International Trends in Geological Disposal and Views on Confidence Building in Radioactive Waste Management; Excavation Disturbed Zone (EDZ) Workshop; Educator's Program and Workshop and a Roundtable on Social Issues in Siting

Report on decision-making of geological disposal. Discussion based on case study

International Nuclear Information System (INIS)

Hiruzawa, Shigenobu

2004-01-01

History of geological disposal from 1950 to 2000 in the world and some examples of change of policy in France, Sweden and Canada are explained. On the case study of three countries, investigations of background of the change, site decision process, communication, flexible concept of disposal are stated. Japan decided the high level radioactive waste is disposed in underground (300m deeper) under the Law Concerning the Final Disposal of Special Radioactive Waste in June, 2000. NUMO (Nuclear Waste Management Organization of Japan) was established to manage disposal of radioactive waste in October, 2000. NUMO started to accept application for the site of disposal in the country in December, 2002. The above case study is a good guide to promote geological disposal of radioactive waste. (S.Y.)

State-of-the-art report on radioactive waste disposal

International Nuclear Information System (INIS)

Larsson, A.

1989-01-01

In view of the considerable work required to develop repositories for radioactive waste, an extensive international co-operation has evolved within the area. The work has also engaged the IAEA to a great extent. The Agency has published a number of reports, covering different aspects of waste disposal. Following a recommendation by its Technical Review Committee on Underground Disposal (TRCUD) the Agency will publish a ''state-of-the-art'' report on radioactive waste disposal. The report is still in the preparation stage. In this article the principal subjects of the future report are discussed

Three Mile Island Cleanup: experiences, waste disposal, and environmental impact

International Nuclear Information System (INIS)

King, L.J.; Opelka, J.H.

1982-01-01

These papers were presented in a two-session symposium during the American Institute of Chemical Engineers 1981 Summer National meeting in Detroit, Michigan, August 16-19, 1981. The cleanup activities described included the venting of the gases, mostly krypton-85, from the reactor containment building and several entries of personnel into the containment building to determine the physical conditions and the levels of radiation and radioactive contamination. Results of the latest process development tests of the flowsheet for the submerged Demineralizer Water Treatment System for decontaminating the water in the containment building were presented. The status of existing knowledge of radiation effects on ion exchange materials used in radioactive waste management were reviewed. A program to demonstrate incorporation of the loaded zeolite into a glass as a final waste form was also described. The generation, classification, treatment, and disposal of solid waste forms resulting from the cleanup were discussed with special consideration of the ion exchange media used for cleanup of liquids with relatively high radionuclide concentrations. The radiological, socioeconomic, and psychological impacts of the cleanup were evaluated. This work formed the basis for the recent issuance by the NRC of a programmatic environmental impact statement relative to decontamination and disposal of the radioactive wastes resulting from the accidents

Performance assessment studies for the long-term safety evaluation of radioactive waste disposal facility

International Nuclear Information System (INIS)

Bujoreanu, D.; Olteanu, M.; Bujoreanu, L.

2008-01-01

the characterization of the disposal facility . In the frame of the performance assessment, sensitivity and uncertainty analyses for the Saligny disposal facility have been conducted, consulting associate activity for the three phases corresponding to the disposal: (i) operational period; (ii) institutionalized control; (iii) post-operative control. In source term evaluating study and of the sensitivity and uncertainty analysis, we took into consideration radionuclide 60 Co, 137 Cs, 3 H and 14 C, these representing the most relevant radionuclide generated by the operation of the nuclear power plant. The sensitivity and uncertainty analysis applies to Saligny disposal facility, correlated with special parameters that are influencing the release of radionuclide from repository, was conducted by using a computer code which yielded results allowing the characterization of the disposal facility at the end of the operational period and to eliminate the uncertainties. (author)

High level radioactive wastes: Considerations on final disposal

International Nuclear Information System (INIS)

Ciallella, Norberto R.

2000-01-01

When at the beginnings of the decade of the 80 the National Commission on Atomic Energy (CNEA) in Argentina decided to study the destination of the high level radioactive wastes, was began many investigations, analysis and multidisciplinary evaluations that be origin to a study of characteristics never before carried out in Argentina. For the first time in the country was faced the study of an environmental eventual problem, several decades before that the problem was presented. The elimination of the high level radioactive wastes in the technological aspects was taken in advance, avoiding to transfer the problems to the future generations. The decision was based, not only in technical evaluations but also in ethical premises, since it was considered that the future generations may enjoy the benefits of the nuclear energy and not should be solve the problem. The CNEA in Argentina in 1980 decided to begin a feasibility study and preliminary engineering project for the construction of the final disposal of high level radioactive wastes

Human health considerations in the assessment of Canadian concept for the disposal of nuclear fuel wastes

International Nuclear Information System (INIS)

Baweja, A.S.; Tracy, B.L.; Ahier, B.; Bartlett, S.

1996-01-01

In 1978, AECL was mandated by the government of Ontario and the federal government to find a permanent disposal solution for spent nuclear fuels. Canada opted for disposal in plutonic rocks of the Canadian shield. The Canadian concept calls for disposal in crystalline rocks at a depth of 500 to 1000 m below the surface. The spent fuel would be contained in a canister, the canister would be emplaced in a vault containing clay-based buffer materials, and the cavity would be backfilled and sealed with natural materials. A Federal Environmental Assessment Review Panel was formed in 1992 to assess the concept for disposal of the spent fuel. In this paper a brief discussion of the human health impacts of the proposed concept is presented. Our assessment is based on the information provided by AECL, namely, the main EIS document, a summary and nine other supporting documents

Public participation and regional development at a nuclear waste disposal site

International Nuclear Information System (INIS)

Ipsen, D.

2005-01-01

The propositions brought forward in this article try to implement sociological aspects into the search for nuclear waste disposal sites based on two theses: Firstly without the willingness of public participation in the search and inspection processes the success of the process is severly put into question in a democratic state. Secondly the potential disposal site must not block the further economic development of the region. These two theses lead to socio-economic criteria for consideration or debarment, to a concept of active and intensive participation, and to considerations about long-term regional development. (orig.)

Final disposal of radioactive wastes. Site selection criteria. Technical and economical factors

International Nuclear Information System (INIS)

Granero, J.J.

1984-01-01

General considerations, geological and socioeconomical criteria for final disposal of radioactive wastes in geological formations are treated. More attention is given to the final disposal of high level radioactive wastes and different solutions searched abroad which seems of interest for Spain. (author)

Considerations in managing the assessment of the Canadian nuclear fuel waste disposal concept

International Nuclear Information System (INIS)

Dormuth, K.W.; Gillespie, P.A.; Whitaker, S.H.

1992-01-01

This paper reports that in developing a concept for disposal of Canada's nuclear fuel waste, AECL has faced challenges because the acceptability of the concept must be established before a site is selected, no agency has been made responsible for implementing the concept if it is selected, and many stakeholders in the review must be satisfied if the concept is to be accepted. The challenges have thus far been met by a program that is well-integrated technically and administratively. However, interactions with stakeholders reviewing the concept present a problem in communication. The authors believe the nature of the nuclear fuel waste disposal issue calls for a cooperative rather than an adversarial approach to problem solving to efficiently deal with the requirements of all the stakeholders

Structures to Resist the Effects of Accidental Explosions. Volume 6. Special Considerations in Explosive Facility Design

Science.gov (United States)

1985-04-01

addition to their Inherent advantages with respect to fire protection, acoustical and thermal insulation, structural mass and resistance to flying...suspended from a monorail system. The panel is inside the shield and is not rigidly attached to the column members. Special consideration was given to...characteristic pulse emitted by an explosion to prevent actuation by other sources such as lightning, fires , etc., **ich cay occur with flash sensors. ■112

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.

Environmental impact assessment of the Swedish high-level radioactive waste disposal system - examples of likely considerations

International Nuclear Information System (INIS)

1994-01-01

Sweden is investigating the feasibility of establishing a high-level radioactive waste (HLW) disposal system consisting of three components as follows: (1) Encapsulation facility, (2) system for transporting waste and (3) geologic repository. Swedish law requires that an Environmental Impact Assessment (EIA) be written for any planned action expected to have a significant impact on the environment. Before embarking on construction and operation of a HLW disposal system, the Swedish government will evaluate the expected environmental impacts to assure that the Swedish people and environmental will not be unduly affected by the disposal system. The EIA process requires that reasonable alternatives to the proposed action, including the 'zero' or 'no action' alternative, be considered so that the final approved plan for disposal will have undergone scrutiny and comparison of alternatives to arrive at a plan which is the best achievable given reasonable physical and monetary constraints. This report has been prepared by the Center for Nuclear Waste Regulatory Analyses (CNWRA) for use by the Swedish Radiation Protection Institute (SSI). The purpose of this report is to establish a document which outlines the types of information which would be in an EIA for a three part disposal system like that envisioned by the Swedish Nuclear Fuel and Waste Management Company (SKB) for the disposal of Sweden's HLW. Technical information that would normally be included in an EIA is outlined in this document. The SSI's primary interest is in radiological impacts. However, for the sake of completeness and also to evaluate all environmental impacts in a single document, non-radiological impacts are also included. Swedish authorities other than the SSI may have interest in the non-radiological parts of the document. 26 refs

S. 705: A Bill to assure fair consideration of the interests of states likely to be affected by the establishment of low-level radioactive waste disposal facilities. Introduced in the Senate of the United States, One Hundredth First Congress, First Session, April 5, 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

S. 705 is a bill to assure fair consideration of the interests of states likely to be affected by the establishment of low-level radioactive waste disposal facilities. Notification of adjacent states is proposed when waste disposal operations are contemplated at border sites

Disposal of drilling fluids and solids generated from water-based systems in Alberta

International Nuclear Information System (INIS)

Parenteau, S.E.

1999-01-01

The different disposal options for drilling wastes as outlined in Guide 50 of the Alberta Energy and Utilities Board (EUB) are discussed. Guide 50 provides for the cost effective and environmentally sound disposal of drilling waste generated in Alberta. Each disposal option of the guide is reviewed and common methods of operation are outlined. Relative costs, environmental suitability and liability issues associated with each option are described. Issues regarding overall disposal considerations, on-site and off-site disposal options, hydrocarbon contamination, salt contaminated waste, toxic waste, and documentation of waste disposal outlined. Some recent programs which have been in the trial phase for a few years are also addressed

Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None, None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Hansen, Francis D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kuhlman, Kristopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sobolik, Steven R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-07-07

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Hansen, Francis D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kuhlman, Kristopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sobolik, Steven R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-07-07

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation, and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

International Nuclear Information System (INIS)

Hansen, Francis D.; Kuhlman, Kristopher L.; Sobolik, Steven R.

2016-01-01

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation, and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences

Special case waste located at Oak Ridge National Laboratory facilities: Survey report

International Nuclear Information System (INIS)

Forgy, J.R. Jr.

1995-11-01

Between October 1994 and October 1995, a data base was established at the Oak Ridge National Laboratory (ORNL) to provide a current inventory of the radioactive waste materials, located at ORNL, for which the US Department of Energy (DOE) has no definite planned disposal alternatives. DOE refers to these waste materials as special case waste. To assist ORNL and DOE management in future planning, an inventory system was established and a baseline inventory prepared. This report provides the background of the ORNL special case waste survey project, as well as special case waste category definitions, both current and anticipated sources and locations of special case waste materials, and the survey and data management processes. Special case waste will be that waste material which, no matter how much practical characterization, treatment, and packaging is made, will never meet the acceptance criteria for permanent disposal at ORNL, and does not meet the criteria at a currently planned off-site permanent disposal facility

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.)

Environmental safety of the disposal system for radioactive substance-contaminated wastes

International Nuclear Information System (INIS)

Oosako, Masahiro

2012-01-01

In accordance with the full-scale enforcement of 'The Act on Special Measures concerning the Handling of Radioactive Pollution' in 2012, the collective efforts of entire Japan for dealing with radioactive pollutants began. The most important item for dealing with radioactive pollution is to control radioactive substances that polluted the global environment and establish a contaminated waste treatment system for risk reduction. On the incineration system and landfill disposal system of radioactive waste, this paper arranges the scientific information up to now, and discusses the safety of the treatment / disposal systems of contaminated waste. As for 'The Act on Special Measures concerning the Handling of Radioactive Pollution,' this paper discusses the points of the Act and basic policy, roadmap for the installation of interim storage facilities, and enforcement regulations (Ordinance of the Ministry of the Environment). About the safety of waste treatment system, it discusses the safety level of technical standards at waste treatment facilities, safety of incineration facilities, and safety of landfill disposal sites. (O.A.)

Nuclear waste disposal: achieving adequate financing - special study

International Nuclear Information System (INIS)

Quasebarth, M.V.

1984-01-01

An analysis by the Congressional Budget Office (CBO) evaluates whether the current one mill fee now charged to nuclear-electricity consumers will adequately finance the waste disposal program. The CBO found that, if the fee is adjusted annually for inflation, it should provide enough revenues to cover all program costs under all nuclear growth forecasts. If the fee is unchanged, however, the fees will be inadequate if inflation exceeds 3% annually. The report suggests two alternatives for fee revision, but makes no recommendations. The alternatives are to increase the fee only at specific intervals or to automatically adjust the fee through indexation. The report examines the effect of delaying the program, cost overruns, and alternative inflation rate and interest rate assumptions. 3 figures, 12 tables

Focusing on clay formation as host media of HLW geological disposal in China

International Nuclear Information System (INIS)

Zheng Hualing; Chen Shi; Sun Donghui

2007-01-01

Host medium is vitally important for safety for HLW geological disposal. Chinese HLW disposal effort in the past decades were mainly focused on granite formation. However, the granite formation has fatal disadvantage for HLW geological disposal. This paper reviews experiences gained and lessons learned in the international community and analyzes key factors affecting the site selection. It is recommended that clay formation should be taken into consideration and additional effort should be made before decision making of host media of HLW disposal in China. (authors)

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)

Health physics considerations in decontamination and decommissioning

International Nuclear Information System (INIS)

1985-12-01

These proceedings contain papers on legal considerations, environmental aspects, decommissioning equipment and methods, instrumentation, applied health physics, waste classification and disposal, and project experience. Separate abstracts have been prepared for individual papers

INERT-MATRIX FUEL: ACTINIDE ''BURNING'' AND DIRECT DISPOSAL

International Nuclear Information System (INIS)

Rodney C. Ewing; Lumin Wang

2002-01-01

Excess actinides result from the dismantlement of nuclear weapons (Pu) and the reprocessing of commercial spent nuclear fuel (mainly 241 Am, 244 Cm and 237 Np). In Europe, Canada and Japan studies have determined much improved efficiencies for burnup of actinides using inert-matrix fuels. This innovative approach also considers the properties of the inert-matrix fuel as a nuclear waste form for direct disposal after one-cycle of burn-up. Direct disposal can considerably reduce cost, processing requirements, and radiation exposure to workers

Main approaches to solving the problems of radioactive waste processing and disposal

International Nuclear Information System (INIS)

Tarasov, V.M.; Syrkus, M.N.

1989-01-01

papers devoted to the problems of processing and disposal of radioactive wastes, formed during nuclear facility operation and after decommissioning are reviewed. Techniques for gaseous and liquid waste solidification, as well as solid waste processing by mechanical fragmentation and combustion are considered. Possibilities of radioactive waste disposal in cosmic space, their burial at the bed of seas ansd oceans, in geological storages are discussed. Special attention disposal. The conclusion is made that today there are no any uniform way for radiactive waste disposal and standard technical means for its realization. Solution of the problems considered should be of a complex character and it is carried out within international research programs

44 CFR 331.4 - Special consideration.

Science.gov (United States)

2010-10-01

... HOMELAND SECURITY PREPAREDNESS PRESERVATION OF THE MOBILIZATION BASE THROUGH THE PLACEMENT OF PROCUREMENT... sells a significant proportion of its production to the Government is generally depressed or has a... hearing of interested parties, will give consideration to appropriate measures applicable to the entire...

Indirect revascularization surgery for moyamoya disease in children and its special considerations

Directory of Open Access Journals (Sweden)

Kyu-Chang Wang

2012-11-01

Full Text Available Moyamoya disease (MMD is the most common pediatric cerebrovascular disease in Far Eastern countries. In children, MMD frequently manifests as ischemic symptomatology. Cerebral perfusion gradually decreases as the disease progresses, which often leads to cerebral infarction. The benefits of revascularization surgery, whether direct or indirect, have been well established in MMD patients with ischemic symptoms. In adults, the increase in cerebral blood flow achieved with indirect revascularization is often unsatisfactory, and direct revascularization is usually feasible. In children, however, direct revascularization is frequently technically not feasible, whereas the response to indirect revascularization is excellent, although 1 or 2 weeks are required for stabilization of symptoms. The authors describe surgical procedures and perioperative care in indirect revascularization for MMD. In addition, special considerations with regard to very young patients, patients with recent cerebral infarction, and patients with hyperthyroidism are discussed.

Preliminary risk benefit assessment for nuclear waste disposal in space

Science.gov (United States)

Rice, E. E.; Denning, R. S.; Friedlander, A. L.; Priest, C. C.

1982-01-01

This paper describes the recent work of the authors on the evaluation of health risk benefits of space disposal of nuclear waste. The paper describes a risk model approach that has been developed to estimate the non-recoverable, cumulative, expected radionuclide release to the earth's biosphere for different options of nuclear waste disposal in space. Risk estimates for the disposal of nuclear waste in a mined geologic repository and the short- and long-term risk estimates for space disposal were developed. The results showed that the preliminary estimates of space disposal risks are low, even with the estimated uncertainty bounds. If calculated release risks for mined geologic repositories remain as low as given by the U.S. DOE, and U.S. EPA requirements continue to be met, then no additional space disposal study effort in the U.S. is warranted at this time. If risks perceived by the public are significant in the acceptance of mined geologic repositories, then consideration of space disposal as a complement to the mined geologic repository is warranted.

Need to use probabilistic risk approach in performance assessment of waste disposal facilities

International Nuclear Information System (INIS)

Bonano, E.J.; Gallegos, D.P.

1991-01-01

Regulations governing the disposal of radioactive, hazardous, and/or mixed wastes will likely require, either directly or indirectly, that the performance of disposal facilities be assessed quantitatively. Such analyses, commonly called ''performance assessments,'' rely on the use of predictive models to arrive at a quantitative estimate of the potential impact of disposal on the environment and the safety and health of the public. It has been recognized that a suite of uncertainties affect the results of a performance assessment. These uncertainties are conventionally categorized as (1) uncertainty in the future state of the disposal system (facility and surrounding medium), (2) uncertainty in models (including conceptual models, mathematical models, and computer codes), and (3) uncertainty in data and parameters. Decisions regarding the suitability of a waste disposal facility must be made in light of these uncertainties. Hence, an approach is needed that would allow the explicit consideration of these uncertainties so that their impact on the estimated consequences of disposal can be evaluated. While most regulations for waste disposal do not prescribe the consideration of uncertainties, it is proposed that, even in such cases, a meaningful decision regarding the suitability of a waste disposal facility cannot be made without considering the impact of the attendant uncertainties. A probabilistic risk assessment (PRA) approach provides the formalism for considering the uncertainties and the technical basis that the decision makers can use in discharging their duties. A PRA methodology developed and demonstrated for the disposal of high-level radioactive waste provides a general framework for assessing the disposal of all types of wastes (radioactive, hazardous, and mixed). 15 refs., 1 fig., 1 tab

Political considerations of nuclear waste disposal policy

International Nuclear Information System (INIS)

Friedman, R.S.

1985-01-01

In order to create a program for the establishment of nuclear waste repositories several conditions must prevail. Perhaps foremost is the need to alter the public perception of risk. In short, there will need to be recognition that cigarette smoking and automobile driving, acts of volition, are potentially more dangerous to one's health than radiation leaks from nuclear power plants or waste repositories. Second, the process of repository site selection will have to include wide public participation in the process in order to obtain legitimacy. Without it Congress and the state legislatures are certain to override any proposal no matter how widely accepted by scientists and engineers. Finally, states and localities selected as sites for repositories will need to be compensated adequately in exchange for accepting the onus of serving as host. Political scientists have not been notably successful forecasters of policy outcomes. However, the evidence of American history does not provide encouragement that maximization of control at the state and local level and oversight by Congress of administrative actions, as meritorious as they might appear in terms of democracy, are harbingers of success for unpleasant policy decisions. States rights and Congressional intervention to block executive action were used to maintain second-class citizenship status for Black Americans until the judicial process was resorted to as a device to alter policy. Most likely, a major policy breakthrough will occur only after a mishap or tragedy, the final product involving either a waste disposal program in the context of continued use of nuclear power or one premised on its abandonment

Nuclear waste disposal: two social criteria

International Nuclear Information System (INIS)

Rochlin, G.I.

1977-01-01

Two criteria--technical irreversibility and site multiplicity--have been suggested for use in establishing standards for the disposal of nuclear wastes. They have been constructed specifically to address the reduction of future risk in the face of inherent uncertainty concerning the social and political developments that might occur over the required periods of waste isolation, to provide for safe disposal without the requirement of a guaranteed future ability to recognize, detect, or repair errors and failures. Decisions as to how to apply or weigh these criteria in conjunction with other waste management goals must be made by societies and their governments. The purpose of this paper was not to preempt this process, but to construct a framework that facilitates consideration of the ethical and normative components of the problem of nuclear waste disposal. The minimum ethical obligation of a waste disposal plan is to examine most thoroughly the potential consequences of present actions, to acknowledge them openly, and to minimize the potential for irremediable harm. An ethically sound waste management policy must reflect not only our knowledge and skills, but our limitations as well

Radioactive waste disposal - policy and perspectives

International Nuclear Information System (INIS)

Roberts, L.E.J.

1979-01-01

Methods are discussed that have been developed and could be used for management and disposal of highly active wastes. The characteristics of such waste are, described and the concept of toxic potential is explained. General principles of waste disposal and the various options which have been considered are discussed. Studies on the incorporation of waste into glass, and on container materials are described. Consideration is also given to the requirements of stores and repositories from the aspect of heat dissipation, design, siting, etc. The advantages and disadvantages of the various types of geological formation ie salt, argillaceous deposits, hardrocks, suitable for containment of highly active wastes are examined. Studies carried out on the safety of repositories and an ocean disposal of the waste are summarised. The review ends with a brief account of the status of the vitrification process in the UK and abroad and of future programmes involving geological and related studies. (UK)

Radioactive waste disposal - policy and perspectives

Energy Technology Data Exchange (ETDEWEB)

Roberts, L E.J. [UKAEA, Harwell. Atomic Energy Research Establishment

1979-04-01

Methods are discussed that have been developed and could be used for management and disposal of highly active wastes. The characteristics of such waste are, described and the concept of toxic potential is explained. General principles of waste disposal and the various options which have been considered are discussed. Studies on the incorporation of waste into glass, and on container materials are described. Consideration is also given to the requirements of stores and repositories from the aspect of heat dissipation, design, siting, etc. The advantages and disadvantages of the various types of geological formation ie salt, argillaceous deposits, hardrocks, suitable for containment of highly active wastes are examined. Studies carried out on the safety of repositories and an ocean disposal of the waste are summarised. The review ends with a brief account of the status of the vitrification process in the UK and abroad and of future programmes involving geological and related studies.

International conference on the safety of radioactive waste disposal. Contributed papers

International Nuclear Information System (INIS)

2005-01-01

The objective of the Conference is to foster information exchange on the safety of radioactive waste disposal covering; the choice of appropriate waste disposal options, safety standards, safety cases for presenting safety arguments and demonstrating compliance with standards, safety assessment methodologies and their application, dealing with uncertainty, regulatory review and decision making, the derivation of limits, controls and conditions to be applied to the development and operation of disposal facilities to ensure safety and the communication of safety issues to all interested stakeholders and confidence development. The conference will consider all possible disposal options available, drawing from experience in Member States with near surface and geological disposal facilities and those at intermediate depths and giving consideration to any multilateral approach that may be adopted. Each of the contributed papers is indexed separately

International conference on the safety of radioactive waste disposal. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The objective of the Conference is to foster information exchange on the safety of radioactive waste disposal covering; the choice of appropriate waste disposal options, safety standards, safety cases for presenting safety arguments and demonstrating compliance with standards, safety assessment methodologies and their application, dealing with uncertainty, regulatory review and decision making, the derivation of limits, controls and conditions to be applied to the development and operation of disposal facilities to ensure safety and the communication of safety issues to all interested stakeholders and confidence development. The conference will consider all possible disposal options available, drawing from experience in Member States with near surface and geological disposal facilities and those at intermediate depths and giving consideration to any multilateral approach that may be adopted. Each of the contributed papers is indexed separately.

Environmental and ethical aspects of long-lived radioactive waste disposal

International Nuclear Information System (INIS)

1994-01-01

All countries engaged in nuclear production give special attention to the safe disposal of radioactive waste, particularly concerning long-term protection of humans and the environment. Many other countries using radioactive materials for medical, industrial or research purposes only are also concerned by this issue. Practically speaking, all countries are generally interested in keeping abreast of the development of radioactive waste management policies and of underlying technical and non-technical studies. These issues and their influence on the decision-making process were examined at a special workshop of the NEA Radioactive Waste Management Committee. This volume presents the full proceedings of that workshop, including papers and transcribed discussions, which sought to provide a broad basis for an in-depth reflection on long-term disposal issues. (authors). 79 refs., 1 tab

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)

41 CFR 102-33.370 - What must we do to dispose of military FSCAP or life-limited parts?

Science.gov (United States)

2010-07-01

... before you exchange or sell the aircraft or engine (see rules for disposing of uninstalled life-limited... dispose of military FSCAP or life-limited parts? 102-33.370 Section 102-33.370 Public Contracts and... Aircraft Parts Special Requirements for Disposing of Flight Safety Critical Aircraft Parts (fscap) and Life...

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.

High-level radioactive waste disposal type and theoretical analyses

International Nuclear Information System (INIS)

Lu Yingfa; Wu Yanchun; Luo Xianqi; Cui Yujun

2006-01-01

Study of high-level radioactive waste disposal is necessary for the nuclear electrical development; the determination of nuclear waste depository type is one of importance safety. Based on the high-level radioactive disposal type, the relative research subjects are proposed, then the fundamental research characteristics of nuclear waste disposition, for instance: mechanical and hydraulic properties of rock mass, saturated and unsaturated seepage, chemical behaviors, behavior of special soil, and gas behavior, etc. are introduced, the relative coupling equations are suggested, and a one dimensional result is proposed. (authors)

Probabilistic safety considerations for the final disposal of radioactive waste

International Nuclear Information System (INIS)

Berg, H.P.; Gruendler, D.; Wurtinger, W.

1992-01-01

In order to demonstrate the safety-related balanced concept of the plant design with respect to the operational phase, probabilistic safety considerations were made for the planned German repository for radioactive wastes, the Konrad repository. These considerations are described with respect to the handling and transfer system in the above-ground and underground facility. The operational sequences and the features of a repository are similar to those of conventional transportation and loading facilities and mining techniques. Hence, failure sequences and probability data were derived from these conventional areas. Incidents taken into consideration are e. g. collision of vehicles, fires, drop of waste packages due to failures of lifting equipment. The statistical data used were made available by authorities, insurance companies, and expert organizations. These data have been converted into probability data which were used for the determination of the frequencies for all radiologically relevant incidents. (author)

Status report on Texas Low-Level Radioactive Waste Disposal Authority activities

International Nuclear Information System (INIS)

Avant, R.V. Jr.

1990-01-01

In 1981, the Texas Low-Level Radioactive Waste Disposal Authority was created by Article 4590f-1 to site, develop, operate, decommission, and close a low-level radioactive waste disposal facility for Texas generated waste. In 1989, the Authority's act was recodified by the Texas legislature in the Health and Safety Code., Title 5. Sanitation and Environmental Quality, Subtitle D. Nuclear and Radioactive Materials, Chapter 402. The Authority is governed by a Board of Directors appointed by the Governor, composed of a certified health physicist, geologist, attorney, medical doctor, and two private citizens. Under the statute, low-level radioactive waste is defined as any radioactive material with a half-life of 35 years or less or having less than 10 nanocuries per gram of transuranics. Materials with half-lives of greater than 35 years may be classed as low-level waste if special criteria are established by the Texas Department of Health Bureau of Radiation Control. Subsequent sessions of the legislature have amended the act to revise siting criteria, require consideration of state land, create a Citizen's Advisory Committee, incorporate alternative designs, and establish a special low-level radioactive waste account in the state treasury. The Authority began its activities in 1982. The Authority has proposed a site in far West Texas near Fort Hancock, but El Paso County, the neighboring county to the west, has instituted three separate lawsuits to slow or stop the site selection process. Particular attention was paid early in the site selection process to items which could be fatal flaws from a licensing standpoint. This paper discusses the Fort Hancock site description, site evaluation studies, siting issues, waste volume projections, facility design, license application, cost and schedule

Development of knowledge building program concerning about high-level radioactive waste disposal

International Nuclear Information System (INIS)

Kimura, Hiroshi; Yamada, Kazuhiro; Takase, Hiroyasu

2005-01-01

Acquirement of knowledge about the high-level radioactive waste (HLW) disposal is one of the important factors for public to determine the social acceptance of HLW disposal. However in Japan, public do not have knowledge about HLW and its disposal sufficiently. In this work, we developed the knowledge building program concerning about HLW disposal based on Nonaka, and Takeuchi's SECI spiral model in knowledge management, and carried to the experiment on this program. In the results, we found that the participants' knowledge about the HLW disposal increased and changed from misunderstanding' or 'assuming' to 'facts' or 'consideration' through this experimental program. These results said that the experimental program leads participants to have higher quality of knowledge about the HLW disposal. In consequence, this knowledge building program may be effective in the acquirement of high quality knowledge. (author)

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

International Nuclear Information System (INIS)

Goldston, W.T.

2000-01-01

Unreviewed Safety Question process examines changes in nuclear facility operations. The process, which ensures that proposed or discovered changes receive the appropriate level of review, is now being used whenever changes such as new waste streams or changes in the design of a waste disposal unit are proposed at SRS. The process involves going through a series of questions to ensure that the change is within the existing performance envelope. Two series of questions are used. The first is a simple screening process. If the change is obviously within the performance envelope, it will be screened from further evaluation. If it cannot be screened, technical personnel involved in the performance assessment, composite analysis, and DAS processes, perform a more detailed evaluation using the second set of questions. If the evaluation shows that the change is within the performance envelope, it can be approved within the contractor's organization. If the evaluation does not clearly conclude t hat the change is within the performance envelope, then a Special Analysis or other more extensive study is triggered. This is a disciplined way to be sure that one knows which changes are significant and which are not, so that the proper attention can be given to the changes that are significant

Consideration of timescales in post-closure safety of geological disposal of radioactive waste

International Nuclear Information System (INIS)

2006-11-01

A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. Over such periods, a wide range of events and processes characterised by many different timescales acts on a repository and its environment. These events and processes, their attendant uncertainties, and their possible impacts on repository evolution and performance must be identified, assessed and communicated in a safety case. The handling of issues related to timescales was discussed at an OECD/NEA workshop held in Paris in 2002 and a short report providing an account of the lessons learnt and issues raised at the workshop, was published in 2004. There is, however, an evolving understanding regarding the nature of the issues related to timescales and how they should be addressed, which provides the motivation for the present report. The report is based on the analysis of the responses to a questionnaire received from twenty-four organisations, representing both implementers and regulators from thirteen OECD member countries, as well as discussions that took place in several later meetings. The report is aimed at interested parties that already have some detailed background knowledge of safety assessment methodologies and safety cases, including safety assessment practitioners and regulators, project managers and scientific specialists in relevant disciplines. Its aims are: - to review the current status and ongoing discussions on the handling of issues related to timescales in the deep geological disposal of long-lived radioactive waste; - to highlight areas of consensus and points of difference between national programmes; and - to determine if there is room for further improvement in methodologies to handle these issues in safety assessment and in building and presenting safety cases. The handling of issues related to timescales in safety cases is affected

Roles of bentonite in radioactive waste disposal

International Nuclear Information System (INIS)

Suzuki, Keizo

1995-01-01

Bentonite is used in radioactive waste disposal from the following points; (1) properties (2) now utilization fields (3) how to use in radioactive waste disposal (4) how much consumption and deposits as source at the present time. Bentonite is produced as alteration products from pyroclastic rocks such as volcanic ash and ryolite, and is clay composed mainly smectite (montmorillonite in general). Therefore, special properties of bentonite such as swelling potential, rheological property, bonding ability, cation exchange capacity and absorption come mainly from properties of montmorillonite. Bentonite has numerous uses such as iron ore pelleizing, civil engineering, green sand molding, cat litter, agricultural chemicals and drilling mud. Consumption of bentonite is about 600-700 x 10 3 tons in Japan and about 10 x 10 6 tons in the world. Roles of bentonite to be expected in radioactive waste disposal are hydraulic conductivity, swelling potential, absorption, mechanical strength, ion diffusion capacity and long-term durability. These properties come from montmorillonite. (author)

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

Energy Technology Data Exchange (ETDEWEB)

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

International Nuclear Information System (INIS)

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-01

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility

Socio-economic impact of improper hospital waste management on waste disposal employees

International Nuclear Information System (INIS)

Khan, M.R.; Raza, Z. L.

2011-01-01

Background: Improper disposal of hospital waste results in spread of disease to the community and its handlers. Objectives: To study the socio-economic impact of inappropriate disposal of hospital waste on the health of the waste disposal staff. Materials and Methods: Interviews were conducted from 50 hospital waste collectors of Lahore and using a pre-structured questionnaire, the information was filled. The data were statistically analyzed for frequencies, and cross tabulation. Results: The improper disposal of hospital waste lead to disease in 45 hospital waste collectors. Eighteen waste collectors were infected with respiratory diseases,14 with skin infection, 7 with tuberculosis and 6 with hepatitis. Only 8 workers were provided with special clothes by the hospital management. The chances of getting infection was high in those who were not provided with special clothes like, gowns, gloves and shoes as compared to those who were provided with these.The total cost of recovery for these diseases also varied with an amount of Rs. 68,340 for the treatment of hepatitis, Rs. 3,150 for tuberculosis, Rs. 1,500 for respiratory diseases and Rs. 1,000 for skin infection. Only 12 workers were given a small remuneration ranging from Rs.100-400 per month as compensation from the hospital administration. Conclusions: Use of protective clothing by the hospital waste disposal collectors can significantly reduce their exposure to the diseases. Policy message: Provision of clothing and gloves to the waste disposal collectors, would help significantly in reducing diseases like tuberculosis, hepatitis, respiratory diseases and skin infection. (author)

Status of disposal techniques for spent fuel in Germany: Results of demonstration tests for direct disposal

International Nuclear Information System (INIS)

Engelmann, H.J.; Filbert, W.

1993-01-01

According to the Atomic Energy Act (1985) the Federal Government is responsible for establishing facilities to indemnify and dispose radioactive waste. According to Art. 9b of the Atomic Energy Act (1986) the construction and operation of such a repository requires approval of a plan. According to safety criteria applicable for disposing radioactive waste in mines, construction and operation of repository mines require application of acknowledged rules of technology, laws, ordinances and other regulations to protect operating staff and population from radiation damages. Shaft hoisting equipment for the transportation of radioactive waste in a repository mine must satisfy normal operational tasks and meet special safety-requirements. Its failure may result in danger for persons, release of radioactive substances into the plant and environment. That means, shaft hoisting equipment must be designed to satisfy the necessary safety requirements and be state of the art of science and technology. The aim of these demonstration tests is verification of technical feasibility of a shaft hoisting equipment with a payload of 85 t, underground for drift disposal of POLLUX-casks, and essential machine and mine-technical systems and components. The demonstration also includes safe radiation protection during transport and disposal operations. Investigations assume that radioactive waste is transported in containers that satisfy transport requirements for dangerous goods and have a type-B-certificate

40 CFR 264.230 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Surface Impoundments § 264.230 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.230 Section 264.230 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

Emplacement and retrieval equipment design considerations for a repository in salt

International Nuclear Information System (INIS)

Nair, B.R.; Bahorich, R.J.

1987-01-01

The current design concept for the disposal of nuclear high level waste packages in a repository in salt is based on the emplacement of individual packages in vertical boreholes in the underground mine floor. A key requirement is that the waste packages be capable of being retrieved during the last 26 years of the 76-year repository operating period. The unique design considerations relating to the retrieval of waste packages emplaced in bedded salt are presented in this paper. The information is based on the experience developed during the design of vertical emplacement and retrieval equipment in support of the Sandia Defense High Level Waste experiments at the Waste Isolation Pilot Plant. Also included are the impact of retrievability on the design of the equipment, the special salt cutting technology that was developed for this application, and a description of the equipment

A review of the justification for exemption orders, and for other low-level radioactive waste disposal practices

International Nuclear Information System (INIS)

Sumerling, T.J.; Sweeney, B.J.

1987-04-01

The historical background and philosophy underlying the Radioactive Substances Act (RSA) and the system of Authorisation and Exemption is examined and the radiological protection criteria contemporary with the introduction of the RSA and those now current are reviewed. The potential radiological impact (maximum individual doses and collective doses to disposal workers and to members of the public) from ''dustbin limit'' disposals, special precautions burial, disposal of demolition wastes, incineration of H-3 and C-14 and from disposals under each of the current Exemption Orders with waste disposal implications are calculated. (author)

Computer-aided evaluation of waste disposal cavern construction methods. ISBN 3-9801713-0-2.

International Nuclear Information System (INIS)

Knissel, W.; Fahlbusch, M.

1991-01-01

The disposal of hazardous radioactive and toxic wastes in deep geological formations is considered the safest solution in many countries. The Federal Republic of Germany prefers salt formations for underground disposal on account of the special advantages of the rock salt. Calculation methods are presented for the mathematical description of mining techniques for the construction of waste disposal salt caverns. The developed calculation model allows one to evaluate different construction methods with regard to expenses and time. (orig./DG) [de

Radiological performance assessment for the E-Area Vaults Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.

2000-01-01

This report is the first revision to ''Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0

Disposal of spent nuclear fuel

International Nuclear Information System (INIS)

1979-12-01

This report addresses the topic of the mined geologic disposal of spent nuclear fuel from Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). Although some fuel processing options are identified, most of the information in this report relates to the isolation of spent fuel in the form it is removed from the reactor. The characteristics of the waste management system and research which relate to spent fuel isolation are discussed. The differences between spent fuel and processed HLW which impact the waste isolation system are defined and evaluated for the nature and extent of that impact. What is known and what needs to be determined about spent fuel as a waste form to design a viable waste isolation system is presented. Other waste forms and programs such as geologic exploration, site characterization and licensing which are generic to all waste forms are also discussed. R and D is being carried out to establish the technical information to develop the methods used for disposal of spent fuel. All evidence to date indicates that there is no reason, based on safety considerations, that spent fuel should not be disposed of as a waste

Health physics aspects in disposal of self powered neutron detectors

International Nuclear Information System (INIS)

Deokar, D.V.; Tibrewala, S.K.; Singh, K.K.; Purohit, R.G.; Tripathi, R.M.

2014-01-01

Self Powered Neutron Detectors (SPNDs) are being used in reactor core for neutron flux measurement at Nuclear Power Plants. After their useful life, SPNDs are replaced and are disposed off in Tile holes. The Cobalt SPNDs having activity in the range of 35 to 160 TBq were encompassed in carbon steel canister. The canister having dose 25 to 50 Sv/h at 1 meter were transported in shielded flask for disposal in specially designed Tile hole at Solid Waste Management Facility (SWMF) at Tarapur. To keep personal exposures As Low As Reasonably Achievable (ALARA) the disposal operation was carried out remotely from a shielded cabin placed at a distance of 50 meter from the disposal site. During the disposal radiation measurements were carried out remotely by installing radiations monitors at a distance of 10 m, 25 m, and 50 m from the Tile hole. Estimations of radiation levels were carried out before jobs were taken up. Disposal of 70 numbers of Cobalt SPNDs was carried out by implementing ALARA. The decrease in collective dose is achieved due to improved operational practices, mock-up trials, effective monitoring program and safety compliance at various stages of operation

An assessment of plant biointrusion at the Uranium Mill Tailings Remedial Action Project rock-covered disposal cells

International Nuclear Information System (INIS)

1990-10-01

This study is one of a number of special studies that have been conducted regarding various aspects of the Uranium Mill Tailings Remedial Action (UMTRA) Project. This special study was proposed following routine surveillance and maintenance surveys and observations reported in a special study of vegetative covers (DOE, 1988), in which plants were observed growing up through the rock erosion layer at recently completed disposal cells. Some of the plants observed were deep-rooted woody species, and questions concerning root intrusion into disposal cells and the need to control plant growth were raised. The special study discussed in this report was designed to address some of the ramifications of plant growth on disposal cells that have rock covers. The NRC has chosen rock covers over vegetative covers in the arid western United States because licenses cannot substantiate that the vegetative covers ''will be significantly greater than 30 percent and preferably 70 percent,'' which is the amount of ''vegetation required to reduce flow to a point of stability.'' The potential impacts of vegetation growing in rock covers are not addressed by the NRC (1990). The objectives, then, of this study were to determine the species of plants growing on two rock-covered disposal cells, study the rooting pattern of plants on these cells, and identify possible impacts of plant root penetration on these and other UMTRA Project rock-covered cells

Selection of heat disposal methods for a Hanford Nuclear Energy Center

International Nuclear Information System (INIS)

Young, J.R.; Kannberg, L.D.; Ramsdell, J.V.; Rickard, W.H.; Watson, D.G.

1976-06-01

Selection of the best method for disposal of the waste heat from a large power generation center requires a comprehensive comparison of the costs and environmental effects. The objective is to identify the heat dissipation method with the minimum total economic and environmental cost. A 20 reactor HNEC will dissipate about 50,000 MWt of waste heat; a 40 reactor HNEC would release about 100,000 MWt. This is a much larger discharge of heat than has occurred from other concentrated industrial facilities and consequently a special analysis is required to determine the permissibility of such a large heat disposal and the best methods of disposal. It is possible that some methods of disposal will not be permissible because of excessive environmental effects or that the optimum disposal method may include a combination of several methods. A preliminary analysis is presented of the Hanford Nuclear Energy Center heat disposal problem to determine the best methods for disposal and any obvious limitations on the amount of heat that can be released. The analysis is based, in part, on information from an interim conceptual study, a heat sink management analysis, and a meteorological analysis

40 CFR 264.199 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Tank Systems § 264.199 Special requirements for incompatible wastes. (a) Incompatible... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.199 Section 264.199 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 264.257 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Waste Piles § 264.257 Special requirements for incompatible wastes. (a) Incompatible... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.257 Section 264.257 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.313 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Landfills § 265.313 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.313 Section 265.313 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.282 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Land Treatment § 265.282 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.282 Section 265.282 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 264.313 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Landfills § 264.313 Special requirements for incompatible wastes. Incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.313 Section 264.313 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

Seismic safety in nuclear-waste disposal

International Nuclear Information System (INIS)

Carpenter, D.W.; Towse, D.

1979-01-01

Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures

Seismic safety in nuclear-waste disposal

Energy Technology Data Exchange (ETDEWEB)

Carpenter, D.W.; Towse, D.

1979-04-26

Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures.

Studies involving proposed waste disposal facilities in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1987-01-01

Today principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries and two research reactors in Turkey. These wastes will be treated in a pilot waste treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200 liter concrete containers until the establishment of the permanent waste disposal sites in Turkey, in 1990. The PRESTO - II (Prediction of Radiation Effects From Shallow Trench Operations) computer code was applied for the general probable sites for LLW disposal in Turkey. The model is non-site specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this codes takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides and use of this contaminated ground water for farming, irrigation, and ingestion

A benefit-cost methodology for developing environmental standards for uranium mill tailings disposal

International Nuclear Information System (INIS)

Leiter, A.J.

1982-01-01

This paper describes a method for using benefit-cost analysis in developing generally applicable environmental standards for uranium mill tailings disposal. Several disposal alternatives were selected which consist of different combinations of control measures. The resulting cost and benefit estimations allow the calculation of the incremental cost of obtaining incremental benefits of radiation protection. The overall benefit of a disposal alternative is expressed in terms of an index which is based on weighting factors assigned to individual benefits. The results show that some disposal alternatives have higher costs while providing no additional benefit than other alternatives. These alternatives should be eliminated from consideration in developing standards

Study of physical resistance of the disposal facility for accidental artificial event in LLW disposal facility

International Nuclear Information System (INIS)

Ogawa, Suihei; Irie, Masaaki; Uchida, Masahiro

2013-11-01

This report refer to results of examine what follows for structural stability evaluation for the LLW disposal facility in depth over general human activity in underground. Study of physically resistance on the facility for accidental artificial event, namely tunneling an operation facing the disposal facility in future. Physically resistance to excavation of tunneling etc. in disposal facility is studied based on supposing of Tunnel Boring Machine as an excavator, paying attention to reinforcement bar in concrete and steel plate of waste package, as feature of strength in these material differs from rock strength. And it is examined not only resistibility on excavation but also about hard situations of excavation in tunneling works, and namely give thorough consideration to critical quantity of cutting to reinforcement bar and steel plate that could keep resistibility on excavation based on tunneling velocity and limits time furthermore. It requests necessity of evaluation in consider with metal corrosion that status alteration on disposal facility is considered with on timescale. Period of keep on the physically resistance is estimated by velocity of metal corrosion consequently. The physically resistance is kept until metal corrosion reach remaining its material, giving a limits of the physically resistance on inside of facility. Main point of physically resistance in the report will be made the good use of a practice to physically resistance evaluation of in safety assessment. (author)

Low-level radioactive waste disposal. Study of a conceptual nuclear energy center at Green River, Utah

International Nuclear Information System (INIS)

Card, D.H.; Hunter, P.H.; Barg, D.; de Souza, F.; Felthauser, K.; Winkler, V.; White, R.

1982-02-01

This document constitutes a segment of a feasibility study investigating the ramifications of constructing a nuclear energy center in an arid western region. In this phase of the study, the alternatives for disposing of the low-level waste on the site are compared with the alternative of transporting the waste to the nearest commercial waste disposal site for permanent disposal. Both radiological and nonradiological impacts on the local socioeconomic infrastructure and the environment are considered. Disposal on the site was found to cost considerably less than off-site disposal with only negligible impacts associated with the disposal option on either mankind or the environment

40 CFR 265.315 - Special requirements for containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for containers..., STORAGE, AND DISPOSAL FACILITIES Landfills § 265.315 Special requirements for containers. Unless they are very small, such as an ampule, containers must be either: (a) At least 90 percent full when placed in...

Tectonic and climatic considerations for deep geological disposal of radioactive waste: A UK perspective.

Science.gov (United States)

McEvoy, F M; Schofield, D I; Shaw, R P; Norris, S

2016-11-15

Identifying and evaluating the factors that might impact on the long-term integrity of a deep Geological Disposal Facility (GDF) and its surrounding geological and surface environment is central to developing a safety case for underground disposal of radioactive waste. The geological environment should be relatively stable and its behaviour adequately predictable so that scientifically sound evaluations of the long-term radiological safety of a GDF can be made. In considering this, it is necessary to take into account natural processes that could affect a GDF or modify its geological environment up to 1millionyears into the future. Key processes considered in this paper include those which result from plate tectonics, such as seismicity and volcanism, as well as climate-related processes, such as erosion, uplift and the effects of glaciation. Understanding the inherent variability of process rates, critical thresholds and likely potential influence of unpredictable perturbations represent significant challenges to predicting the natural environment. From a plate-tectonic perspective, a one million year time frame represents a very short segment of geological time and is largely below the current resolution of observation of past processes. Similarly, predicting climate system evolution on such time-scales, particularly beyond 200ka AP is highly uncertain, relying on estimating the extremes within which climate and related processes may vary with reasonable confidence. The paper highlights some of the challenges facing a deep geological disposal program in the UK to review understanding of the natural changes that may affect siting and design of a GDF. Crown Copyright © 2016. Published by Elsevier B.V. All rights reserved.

40 CFR 264.177 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Use and Management of Containers § 264.177 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.177 Section 264.177 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.199 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Tank Systems § 265.199 Special requirements for incompatible wastes. (a... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.199 Section 265.199 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.257 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Waste Piles § 265.257 Special requirements for incompatible wastes. (a... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.257 Section 265.257 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 264.282 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Land Treatment § 264.282 Special requirements for incompatible wastes. The owner or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.282 Section 264.282 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

Study of extraterrestrial disposal of radioactive wastes. Part 1: Space transportation and destination considerations for extraterrestrial disposal of radioactive wastes. [feasibility of using space shuttle

Science.gov (United States)

Thompson, R. L.; Ramler, J. R.; Stevenson, S. M.

1974-01-01

A feasibility study of extraterrestrial disposal of radioactive waste is reported. This report covers the initial work done on only one part of the NASA study, that evaluates and compares possible space destinations and space transportation systems. The currently planned space shuttle was found to be more cost effective than current expendable launch vehicles by about a factor of 2. The space shuttle requires a third stage to perform the waste disposal missions. Depending on the particular mission, this third stage could be either a reusable space tug or an expendable stage such as a Centaur.

Legal and regulatory issues regarding classification and disposal of wastes from actinide partitioning and transmutation

International Nuclear Information System (INIS)

Kocher, D.C.

1989-01-01

Partitioning and transmutation of actinide radioelements in spent nuclear fuel from civilian power reactors is potentially attractive because the resulting wastes might be acceptable for disposal using systems which are considerably less costly than a deep geologic repository. At present, there are no legal or regulatory prohibitions to seeking alternatives to a geologic repository for disposal of such wastes. However, additional laws and regulations would be needed, and the Nuclear Regulatory Commission has been reluctant to alter the current framework for radioactive waste management, in which geologic repositories or near-surface facilities are the only disposal options established in law and regulations unless a compelling need for alternatives with intermediate waste-isolation capabilities is demonstrated. There are also important technical considerations which are not encouraging with regard to the development of intermediate disposal systems for wastes from partitioning and transmutation of actinides in civilian spent fuel. First, the wastes may contain sufficient concentrations of fission products. Second, defense reprocessing wastes may contain sufficient concentrations of fission products and long-lived actinides. Thus, in developing the legal and regulatory framework for alternative disposal systems, there is a need to establish maximum concentrations of fission products and long-lived actinides that would be acceptable for intermediate disposal. 19 refs

Disposal of high-level waste from nuclear power plants in Denmark. Salt dome investigations. v.5

International Nuclear Information System (INIS)

1981-01-01

The present report deals with safety evaluation as part of the investigations regarding a repository for high-level waste in a salt dome. It is volume 5 of five volumes that together constitute the final report on the Danish utilities' salt dome investigations. Two characteristics of the waste are of special importance for the safety evaluation: the encasing of the waste in steel casks with 15 cm thick walls affording protection against corrosion, protecting the surroundings against radiation, and protecting the glass cylinders from mechanical damage resulting from the pressure at the bottom of the disposal hole, and the modest generation of heat in the waste at the time of disposal resulting in a maximum temperature increase in the salt close to the waste of approx. 40 deg. C. These characteristics proved to considerably improve the safety margin with respect to unforeseen circumstances. The character of the salt dome and of the salt in the proposed disposal area offers in itself good protection against contact with the ground water outside the dome. The relatively large depth of 1200 and 2500 m of the salt surface also means that neither dome nor disposal facility will be appreciably influenced by glaciations or earthquakes. The chalk above the proposed disposal area is very tight and to retain radioactive matter effectively even in the precence of high concentrations of NaCL. The safety investigations included a number of natural processes and probable events such as the segregation of crystal water from overlooked salt minerals, faulty sealings of disposal holes, permeable fault zones in the chalk overlying the dome, the risk in connection with human penetration into the dome. These conditions will neither lead to the destruction of the waste casks or to the release of waste from the dome. Leaching of a cavern is the only situation which proved to result in a release of radioactive material to the biosphere, but the resulting doses was found to be small

Performance assessment for future low-level waste disposal facilities at ORNL

International Nuclear Information System (INIS)

Lee, D.W.; Kocher, D.C.

1989-01-01

This paper discusses the strategy for waste management on the Oak Ridge Reservation (ORR) and the approach to preparing future performance assessments that has evolved from previous performance assessment studies of low-level radioactive waste disposal on the ORR. The strategy for waste management is based on the concept that waste classification should be determined by performance assessment other than the sources of waste. This dose-based strategy for waste classification and management places special importance on the preparation and interpretation of waste disposal performance assessments for selecting appropriate disposal technologies and developing waste acceptance criteria. Additionally, the challenges to be overcome in the preparation of performance assessments are discussed. 7 refs

Selection of radioactive waste disposal site considering natural processes

International Nuclear Information System (INIS)

Nakamura, H.

1991-01-01

To dispose the radioactive waste, it is necessary to consider the transfer of material in natural environment. The points of consideration are 1) Long residence time of water 2) Independence of biosphere from the compartment containing the disposal site in the natural hydrologic cycle 3) Dilution with the natural inactive isotope or the same group of elements. Isotope dilution for 129 I and 14 C can be expected by proper selection of the site. 241 Am and 239 Pu will be homogenized into soil or sediment with insoluble elements such as iron and aluminium. For 237 Np and 99 Tc anionic condition is important for the selection. From the point of view of hydrologic cycle, anoxic dead water zone avoiding beneath mountain area is preferable for the disposal site. (author)

Framework for DOE mixed low-level waste disposal: Site fact sheets

Energy Technology Data Exchange (ETDEWEB)

Gruebel, M.M.; Waters, R.D.; Hospelhorn, M.B.; Chu, M.S.Y. [eds.

1994-11-01

The Department of Energy (DOE) is required to prepare and submit Site Treatment Plans (STPS) pursuant to the Federal Facility Compliance Act (FFCAct). Although the FFCAct does not require that disposal be addressed in the STPS, the DOE and the States recognize that treatment of mixed low-level waste will result in residues that will require disposal in either low-level waste or mixed low-level waste disposal facilities. As a result, the DOE is working with the States to define and develop a process for evaluating disposal-site suitability in concert with the FFCAct and development of the STPS. Forty-nine potential disposal sites were screened; preliminary screening criteria reduced the number of sites for consideration to twenty-six. The DOE then prepared fact sheets for the remaining sites. These fact sheets provided additional site-specific information for understanding the strengths and weaknesses of the twenty-six sites as potential disposal sites. The information also provided the basis for discussion among affected States and the DOE in recommending sites for more detailed evaluation.

Radioactive wastes: sources, treatment, and disposal

International Nuclear Information System (INIS)

Wymer, R.G.; Blomeke, J.O.

1975-01-01

Sources, treatment, and disposal of radioactive wastes are analyzed in an attempt to place a consideration of the problem of permanent disposal at the level of established or easily attainable technology. In addition to citing the natural radioactivity present in the biosphere, the radioactive waste generated at each phase of the fuel cycle (mills, fabrication plants, reactors, reprocessing plants) is evaluated. The three treatment processes discussed are preliminary storage to permit decay of the short-lived radioisotopes, solidification of aqueous wastes, and partitioning the long-lived α emitters for separate and long-term storage. Dispersion of radioactive gases to the atmosphere is already being done, and storage in geologically stable structures such as salt mines is under active study. The transmutation of high-level wastes appears feasible in principle, but exceedingly difficult to develop

Radiological protection objectives for the disposal of solid radioactive wastes

International Nuclear Information System (INIS)

1983-10-01

Guidance is given on the standards to be used in the UK in decisions on the radiological acceptability of disposal methods for solid radioactive wastes. The radiological protection objectives given in the report are intended to be applied to all types of solid radioactive waste, and to all the disposal methods which are in use or under consideration. This guidance complements and extends previous Board advice on radiological protection objectives which apply to the control of routine discharges of gaseous and liquid effluents. (author)

The choice of locations for disposal of dangerous (radioactive) waste

International Nuclear Information System (INIS)

Hisschemoller, M.; Midden, C.J.H.; Stallen, P.J.; Rijksuniversiteit Leiden; Nederlandse Centrale Organisatie voor Toegepast Natuurwetenschappelijk Onderzoek, The Hague)

1985-11-01

In this report a managerial and psychological analysis, based on literature study and case analysis, is presented of various policy strategies which are or can be followed by governments in decisions about disposal of dangerous waste. Special attention is given to radioactive waste. (Auth.)

Cost effectiveness of below-threshold waste disposal at DOE sites

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.

1987-01-01

A minimal health and environmental risk, limitations on disposal capacity, and the relatively high costs of low level waste (LLW) disposal are basic driving forces that lead to consideration of less restrictive disposal of wastes with very low levels of radiological contamination. The term threshold limit describes radioactive wastes that have sufficiently low-levels of radiological content to be managed according to their nonradiological properties. Given the efforts described elsewhere to provide guidance on the definition of below threshold (BT) doses and concentration levels, the purpose of this study was to quantify the resultant quantities, costs and cost effectiveness of BT disposal. For purposes of consistency with the previous demonstrations of the application of the threshold concept, available data for waste streams at the Idaho National Engineering Laboratory (INEL) and the Savannah River Plant (SRP) sites were collected and analyzed with regard to volumes, radionuclide concentrations, and disposal costs. From this information, quantities of BT waste, potential cost savings and cost effectiveness values were estimated. 1 reference, 5 tables

Status report on the disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Culler, F.L. Jr.; McLain, S. (comps.)

1957-06-25

A comprehensive survey of waste disposal techniques, requirements, costs, hazards, and long-range considerations is presented. The nature of high level wastes from reactors and chemical processes, in the form of fission product gases, waste solutions, solid wastes, and particulate solids in gas phase, is described. Growth predictions for nuclear reactor capacity and the associated fission product and transplutonic waste problem are made and discussed on the basis of present knowledge. Biological hazards from accumulated wastes and potential hazards from reactor accidents, ore and feed material processing, chemical reprocessing plants, and handling of fissionable and fertile material after irradiation and decontamination are surveyed. The waste transportation problem is considered from the standpoints of magnitude of the problem, present regulations, costs, and cooling periods. The possibilities for ultimate waste management and/or disposal are reviewed and discussed. The costs of disposal, evaporation, storage tanks, and drum-drying are considered.

Current status of high level radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Tanaka, Satoru; Tanabe, Hiromi; Inagaki, Yusuke; Ishida, Hisahiro; Kato, Osamu; Kurata, Mitsuyuki; Yamachika, Hidehiko

2002-01-01

At a time point of 2002, there is no country actually disposing high level radioactive wastes into grounds, but in most of countries legislative preparation and practicing agents are carried out and site selection is promoted together with energetic advancement of its R and Ds. As disposal methods of the high level radioactive wastes, various methods such as space disposal, oceanic bottom disposal, ice bed disposal, ground disposal, and so on have been examined. And, a processing technology called partitioning and transmutation technology separating long-lived radionuclides from liquid high level radioactive waste and transmutation into short-lived or harmless radionuclides has also been studied. Here was introduced their wrestling conditions in Japan and main foreign countries, as a special issue of the Current status of high level radioactive waste disposal in Japan and foreign countries'. The high level radioactive wastes (glassification solids or spent nuclear fuels) are wastes always formed by nuclear power generation and establishment of technologies is an important subject for nuclear fuel cycle. (G.K.)

Environmental considerations in the selection of isolation gowns: A life cycle assessment of reusable and disposable alternatives.

Science.gov (United States)

Vozzola, Eric; Overcash, Michael; Griffing, Evan

2018-04-11

Isolation gowns serve a critical role in infection control by protecting healthcare workers, visitors, and patients from the transfer of microorganisms and body fluids. The decision of whether to use a reusable or disposable garment system is a selection process based on factors including sustainability, barrier effectiveness, cost, and comfort. Environmental sustainability is increasingly being used in the decision-making process. Life cycle assessment is the most comprehensive and widely used tool used to evaluate environmental performance. The environmental impacts of market-representative reusable and disposable isolation gown systems were compared using standard life cycle assessment procedures. The basis of comparison was 1,000 isolation gown uses in a healthcare setting. The scope included the manufacture, use, and end-of-life stages of the gown systems. At the healthcare facility, compared to the disposable gown system, the reusable gown system showed a 28% reduction in energy consumption, a 30% reduction in greenhouse gas emissions, a 41% reduction in blue water consumption, and a 93% reduction in solid waste generation. Selecting reusable garment systems may result in significant environmental benefits compared to selecting disposable garment systems. By selecting reusable isolation gowns, healthcare facilities can add these quantitative benefits directly to their sustainability scorecards. Copyright © 2018 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

Geologic and hydrologic considerations for various concepts of high-level radioactive waste disposal in conterminous United States

International Nuclear Information System (INIS)

Ekren, E.B.; Dinwiddie, G.A.; Mytton, J.W.; Thordarson, W.; Weir, J.E. Jr.; Hinrichs, E.N.; Schroder, L.J.

1974-01-01

The purpose of this investigation is to evaluate and identify which geohydrologic environments in conterminous United States are best suited for various concepts or methods of underground disposal of high-level radioactive wastes and to establish geologic and hydrologic criteria that are pertinent to high-level waste disposal. The unproven methods of disposal include (1) a very deep drill hole (30,000 to 50,000 ft or 9,140 to 15,240 m), (2) a matrix of (an array of multiple) drill holes (1,000 to 20,000 ft or 305 to 6,100 m), (3) a mined chamber (1,000 to 10,000 ft or 305 to 3,050 m), (4) a cavity with separate manmade structures (1,000 to 10,000 ft or 305 to 3,050 m), and (5) an exploded cavity (2,000 to 20,000 ft or 610 to 6,100 m). Areas considered to be unsuitable for waste disposal are those where seismic risk is high, where possible sea-level rise would inundate potential sites, where high topographic relief coincides with high frequency of faults, where there are unfavorable ground-water conditions, and where no suitable rocks are known to be present to depths of 20,000 feet (6,100 m) or more, and where these strata either contain large volumes of ground water or have high oil and gas potential

DOE handbook: Design considerations

International Nuclear Information System (INIS)

1999-04-01

The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline

DOE handbook: Design considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline.

Economic and energy analysis about disposal interventions of waste tires produced in Calabria

International Nuclear Information System (INIS)

Florio, Gaetano; Cersosimo, Attilio.

1997-01-01

The present paper refers to an analysis aimed at researching disposal strategies, for waste tires produced in Calabria, which ensure correct disposal with regard to environmental compatibility and their evaluation in terms of material recovery and energy. The starting point has been an estimate of the quantities of potentially usable waste tires and disposal methods currently employed. It has therefore been possible to identify two specific disposal proposals for which an economic and energy evaluation has been conducted. The last part of the paper has faced the problem of plant location under consideration, with the aim of determining, for both proposal, the cost that each producer must bear to have his waste tires eliminated

Safety and performance assessment of geologic disposal systems for nuclear wastes

International Nuclear Information System (INIS)

Peltonen, E.

1987-01-01

This thesis presents a methodology for the safety and performance assesment of final disposal of nuclear wastes into crystalline bedrock. The applicability of radiation protection objectives is discussed, as well as the goals of the assessment in the various repository system development phases. Due consideration is given to the description of the pertinent analysis methods and to the comprehensive model system. The methodology has been applied to assess the acceptability of the basic disposal concepts and to study the possibilities for the optimization of protection. Furthermore, performance of different components in the multiple barrier disposal systems is estimated. The waste types dealt with are low- and intermediate-level waste as well as high-level spent nuclear fuel from a nuclear power plant. In addition, an option of high-level vitrified waste from reprocessing of spent fuel is taken into account. On the basis of the various analyses carried out it can be concluded that the disposal of different nuclear wastes in the Finnish bedrock in properly designed repositories meets the radiation protection objectives with good confidence. In addition, the studies indicate that the safety margins are considerable. This is due to the fact that the overall performance of the multiple barrier disposal systems analysed is not sensitive to possible unfavourable changes in barrier properties. From the optimization of protection point of view it can be concluded that there is no need to develop more effective repository designs than those analysed in this thesis. In fact, the results indicate that the most sophisticated designs have already gone beyond an optimal level of safety

Geoenvironmental considerations for assessments of the potential of solid waste disposal in rural Lebanon, Metn-Kesserwan

International Nuclear Information System (INIS)

Nasser, Rima Souheil

1994-02-01

This investigation deals with the problem capitalizing on a mountainous area in Lebanon, and allocating potential sanitary landfill sites for solid waste disposal. The current solid waste management scheme is studied through questionnaires distributed to the community, and field investigations on the operation and effects of the final dump sites. The assessment of the potential for solid waste disposal is approached through evaluating the general suitability of that area for sanitary land filling. This is done by studying various socio-economic and technical parameters on both existing dump sites and others that are here proposed. The environmental impacts of existing dump sites are also described; a modified drastic scheme is used to assess potential ground water pollution in these sites. All of the sites ranked high with respect to their potential pollution of ground water. This is mainly due to their being located directly over highly fractured and karstified limestones. Four areas that proved favourable, in suitability analysis, for solid waste disposal are further subjected to geotechnical investigations to arrive at their capability for sanitary land filling. These include permeability, texture, particle density, Atterberg limits, organic content, clay content and type. As a result of capability analysis, the four sites are ranked from most to least capable for sanitary land filling, according to a quantified weighted rating scale. Sanitary land filling is thus proposed. Solid waste disposal, however, must be followed through an integrated management approach which includes, in addition to land filling, composting, incineration and recycling in a comprehensive waste management scheme. These alternatives are discussed in view of their advantages and disadvantages

A laboratory evaluation of two brands of disposable air turbine handpiece.

Science.gov (United States)

Dyson, J E; Darvell, B W

1997-01-11

To report on the essential performance characteristics of two brands of disposable air turbine handpiece and on aspects of their safety and convenience for clinical use. Oralsafe and Feathertouch disposable handpieces were characterised using a variety of techniques in respect of the following: turbine rotor radius, equivalent orifice radius, stall torque coefficient, pressure effectiveness, power index, efficiency index, sound level and instrument retention force. Free-running speed versus pressure curves for many of the disposable handpieces showed marked deviations from the expected smooth form. Considerable variation between examples of each type was found in most measured values. Evidence of eccentric rotors and high bearing friction was not found. Both brands of disposable handpiece had a number of problems: poor performance, vibration, excessive noise, variability of behaviour, poor bearings. Use of these devices is difficult to recommend. Improvement in design seems necessary.

Considerations in recycling contaminated scrap metal and rubble

International Nuclear Information System (INIS)

Kluk, A.F.; Hocking, E.K.

1992-01-01

Management options for the Department of Energy's increasing amounts of contaminated scrap metal and rubble include reuse as is, disposal, and recycling. Recycling, with its promise of resource recovery, virgin materials conservation, and land disposal minimization, emerges as a preferred management technique. Implementing a cost effective recycling program requires resolution of several issues including: establishing release limits for contaminants, controlling use of recycled materials creating effective public communication programs; developing economical, reliable assay technologies; managing secondary waste streams, expanding availability of unrestricted markets; and solving conflicting legal considerations

Disposal of Canada's nuclear fuel waste

International Nuclear Information System (INIS)

Dormuth, K.W.; Nuttall, K.

1994-01-01

In 1978, the governments of Canada and Ontario established the Nuclear Fuel Waste Management program. As of the time of the conference, the research performed by AECL was jointly funded by AECL and Ontario Hydro through the CANDU owners' group. Ontario Hydro have also done some of the research on disposal containers and vault seals. From 1978 to 1992, AECL's research and development on disposal cost about C$413 million, of which C$305 was from funds provided to AECL by the federal government, and C$77 million was from Ontario Hydro. The concept involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield. Used fuel (or possibly solidified reprocessing waste) would be sealed into containers (of copper, titanium or special steel) and emplaced (probably in boreholes) in the vault floor, surrounded by sealing material (buffer). Disposal rooms might be excavated on more than one level. Eventually all excavated openings in the rock would be backfilled and sealed. Research is organized under the following headings: disposal container, waste form, vault seals, geosphere, surface environment, total system, assessment of environmental effects. A federal Environmental Assessment Panel is assessing the concept (holding public hearings for the purpose) and will eventually make recommendations to assist the governments of Canada and Ontario in deciding whether to accept the concept, and how to manage nuclear fuel waste. 16 refs., 1 tab., 3 figs

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

Radiological Operational Safety Verification for LILW Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Ju Youl [FNC Technology, SNU, Seoul (Korea, Republic of); Jeong, Seung Young; Kim, Byung Soo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2011-10-15

component (chemistry). They can be measured using proven equipment and methods such as wireless and non-intrusive monitoring techniques. Directly accessing the waste packages for the purpose of monitoring could negatively affect the long-term performance of engineered barriers. One way to solve this problem is to build a pilot facility (demonstration facility) at another site set apart from the actual disposal site and implement monitoring there. The pilot facility proposed by the 'Expert Group on Disposal Concepts for Radioactive Waste' of Switzerland is a small-scale facility which is different from test facility (in-situ rock laboratory) in terms of representative amount of real waste. The pilot facility provides information to confirm the performance of the repository system, and also allows the early detection of any deviations from the expected evolution. National low-level waste management program of the United States published a report containing 16 key radionuclides that are judged by the NRC to most likely contribute significantly to the radiation exposures estimated from a performance assessment of a proposed commercial LLW disposal facility. They are {sup 3}H, {sup 14}C, {sup 60}Co, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 137}Cs, {sup 237}Np, {sup 238}U, {sup 239}Pu, {sup 241}Pu, {sup 241}Am, {sup 242}Cm. They are almost consistent with concentration limits of radionuclides for disposal of No. of Notices of the MOST: 2009-37 except gross alpha radioactivity (TRU) and {sup 238}U. Four radionuclides, such as {sup 3}H, {sup 14}C, {sup 99}Tc and {sup 129}I, are identified as special considerations by the NRC in terms of ensuring that performance objectives for long-term environmental protection are met for disposal of commercial LLW. They are very mobile in groundwater, and their main route to enter the human body is by either ingestion or inhalation

Advice on the disposal of radioactive by-products arising in the use of nuclear energy

International Nuclear Information System (INIS)

Beyermann, M.; Goergner, D.

1989-01-01

Based on the current legislation in the GDR advice is given on the classification and disposal of radioactive by-products from the utilization of nuclear energy with special emphasis on the different procedures for products which require a disposal licence by the National Board for Atomic Safety and Radiation Protection and those which do not need such an authorization. (author)

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

Modelling approach to evaluate safety of LILW-SL disposal in slovenia considering different waste packaging options

International Nuclear Information System (INIS)

Perko, J.; Mallants, D.

2007-01-01

The long-term safety of radioactive waste repositories is usually demonstrated by means of a safety assessment which normally includes modelling of radionuclide release from a multi-barrier surface or deep repository to the geosphere and biosphere. The present quantitative evaluation performed emphasizes on contrasting disposal options under consideration in Slovenia and concerns siting, disposal concept (deep versus surface), and waste packaging. The assessment has identified a number of conditions that would lead to acceptable waste disposal solutions, while at the same time results also revealed options that would result in exceeding the radiological criteria. Results presented are the output of a collective effort of a Quintessa-led Consortium with SCK-CEN and Belgatom, in the framework of a recent PHARE project. The key objective of this work was to identify the preferred disposal concept and packaging option from a number of alternatives being considered by the Slovenian radioactive waste management agency (ARAO) for low and intermediate level short-lived waste (LILW-SL). The emphasis of the assessment was the consideration of several waste treatment and packaging options in an attempt to identify the minimum required containment characteristics which would result in safe disposal and the cost-benefit of additional safety measures. Waste streams for which alternative treatment and packaging solutions were developed and evaluated include decommissioning waste and NPP operational wastes containing drums with unconditioned ion exchange resins in overpacked tube type containers (TTCs). For the former the disposal options under consideration were either direct disposal of loose pieces grouted into a vault or use of high integrity containers. For the latter three options were foreseen. The first is overpacking of resin containing TTCs grouted into high integrity containers, the second option is complete treatment with hydration, neutralisation, and cementation of

Alternative disposal options for alpha-mixed low-level waste

International Nuclear Information System (INIS)

Loomis, G.G.; Sherick, M.J.

1995-01-01

This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas systems with secondary waste management problems. In the United States, public perception of offgas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option

Alternative disposal options for alpha-mixed low-level waste

Energy Technology Data Exchange (ETDEWEB)

Loomis, G.G.; Sherick, M.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1995-12-31

This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas, systems with secondary waste management problems. In the United States, public perception of off gas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option.

Standards for high level waste disposal: A sustainability perspective

International Nuclear Information System (INIS)

Dougherty, W.W.; Powers, V.; Johnson, F.X.; Cornland, D.

1999-01-01

Spent reactor fuel from commercial power stations contains high levels of plutonium, other fissionable actinides, and fission products, all of which pose serious challenges for permanent disposal because of the very long half-lives of some isotopes. The 'nuclear nations' have agreed on the use of permanent geologic repositories for the ultimate disposal of high-level nuclear waste. However, it is premature to claim that a geologic repository offers permanent isolation from the biosphere, given high levels of uncertainty, nascent risk assessment frameworks for the time periods considered, and serious intergenerational equity issues. Many have argued for a broader consideration of disposal options that include extended monitored retrievable storage and accelerator-driven transmutation of wastes. In this paper we discuss and compare these three options relative to standards that emerge from the application of sustainable development principles, namely long-lasting technical viability, intergenerational equity, rational resource allocation, and rights of future intervention. We conclude that in order to maximise the autonomy of future generations, it is imperative to leave future options more open than does permanent disposal

Equity and nuclear waste disposal

International Nuclear Information System (INIS)

Shrader-Frechette, K.

1994-01-01

Following the recommendations of the US National Academy of Sciences and the mandates of the 1987 Nuclear Waste Policy Amendments Act, the US Department of Energy has proposed Yucca Mountain, Nevada as the site of the world's first permanent repository for high-level nuclear waste. The main justification for permanent disposal (as opposed to above-ground storage) is that it guarantees safety by means of waste isolation. This essay argues, however, that considerations of equity (safer for whom?) undercut the safety rationale. The article surveys some prima facie arguments for equity in the distribution of radwaste risks and then evaluates four objections that are based, respectively, on practicality, compensation for risks, scepticism about duties to future generations, and the uranium criterion. The conclusion is that, at least under existing regulations and policies, permanent waste disposal is highly questionable, in part, because it fails to distribute risk equitably or to compensate, in full, for this inequity

Siting of geological disposal facilities

International Nuclear Information System (INIS)

1994-01-01

Radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials in industrial applications, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. The Radioactive Waste Safety Standards (RADWASS) programme is the IAEA's contribution to establishing and promoting the basic safety philosophy for radioactive waste management and the steps necessary to ensure its implementation. This Safety Guide defines the process to be used and guidelines to be considered in selecting sites for deep geological disposal of radioactive wastes. It reflects the collective experience of eleven Member States having programmes to dispose of spent fuel, high level and long lived radioactive waste. In addition to the technical factors important to site performance, the Safety Guide also addresses the social, economic and environmental factors to be considered in site selection. 3 refs

The scientific and regulatory basis for the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Savage, D.

1995-01-01

The disposal of radioactive waste is a central issue in the future of nuclear power and poses considerable technical, political and social issues. This book addresses these topics in an integrated fashion using performance assessment of the disposal concept as a unifying theme. Subjects addressed include: regulatory criteria; waste types, sources and characteristics; man-made or ''engineered'' barriers; the selection and evaluation of geological disposal media; the use of underground research laboratories; the movement of radionuclides in the biosphere; repository performance assessment tools approaches; addressing uncertainty and spatial variability; assessing information from natural systems; and looking at radioactive waste in relation to other wastes. (Author)

Safety related aspects of ultimate disposal of radioactive wastes

International Nuclear Information System (INIS)

Goemmel, R.

1992-01-01

Solutions and questions related to nuclear waste management are presented. In particular, long-term safety of repositories in Germany and Sweden is considered, with special attention being paid to methods of detection, geotechnical barriers and post-operational phase of salt dome repositories, and conditioning of wastes to make them fit for ultimate disposal. (DG) [de

Water quality considerations resulting in the impaired injectivity of water injection and disposal wells

International Nuclear Information System (INIS)

Bennion, D.B.; Thomas, F.B.; Imer, D.; Ma, T.

2000-01-01

An environmentally responsible way to improve hydrocarbon recovery is to maintain pressure by water injection. This is a desirable method because unwanted produced water from oil and gas wells can be re-injected into producing or disposal formations. The success of the operation, however, depends on injecting the necessary volume of water economically, below the fracture gradient pressure of the formation. Well placement, geometry and inherent formation quality and relative permeability characteristics are some of the many other factors which influence the success of any injection project. Poor injection or poor quality of disposal water can also compromise the injectivity for even high quality sandstone or carbonate formations. This would necessitate costly workovers and recompletions. This paper presented some leading edge diagnostic techniques and evaluation methods to determine the quality of injected water. The same techniques could be used to better understand the effect of potential contaminants such as suspended solids, corrosion products, skim/carryover oil and grease, scales, precipitates, emulsions, oil wet hydrocarbon agglomerates and many other conditions which cause injectivity degradation. 14 refs., 1 tab., 15 figs

Determining criteria for the disposal of iodine-129

International Nuclear Information System (INIS)

Burger, L.L.

1980-10-01

The basic consideration in the disposal of the 129 I produced by the nuclear power industry is that humans must be protected from unacceptable radiation risks. Existing standards prescribe maximum concentrations in air and water and, more recently, a maximum release per unit of electrical power production. The global quantity, distribution, and rate of movement of 127 I (natural iodine), naturally produced 129 I, and anthropogenic 129 I are examined. The 129 I released earlier as a result of nuclear activities over the past few decades is not uniformly dispersed. But the possibility of much greater dispersion exists and, therefore, of much greater dilution than was previously attempted. The potential for dilution with respect to either the 129 I concentration or the 129 I/ 127 I ratio far exceeds the minimum required for acceptable exposure to mankind. For utilizing the dilution principle, it is preferable to package and dispose of 129 I separately from other fission products. The deep ocean is seen to be the logical location for ultimate disposal. A set of 14 basic items is described that can be used to set criteria for storage and disposal of 129 I. It is suggested that preliminary standards be developed on these and perhaps other items to apply to (1) temporary storage and transportation, (2) disposal to a dry environment with a time limitation on calculated behavior, and (3) disposal to the deep ocean with complete release permitted in 10 3 yr. Early quantification of some of these items will permit better decisions on further research and development needed for iodine removal or control, fixation, and disposal

R and D projects for disposal concepts for special radioactive wastes

International Nuclear Information System (INIS)

1983-01-01

Updated requirements for the elaboration of reference methods or back-up methods for the conditioning and ultimate storage of special radioactive wastes are worked out. Subsequently, the present state-of-art and ongoing studies are analyzed. Special radioactive wastes collected in collecting points, or produced in medicine and industry are included in the paper. With special unclear wastes, the emphasis is on wastes from LWR-type reactors and those from the unclear fuel cycle. The PTB data base is to by complemented by the characterization of waste compounds with volatile nuclides. 16 specialist contributions have been included in the data base. (HP) [de

Research and development plans for disposal of high-level and transuranic wastes

International Nuclear Information System (INIS)

Bartlett, J.W.; Platt, A.M.

1978-09-01

This plan recommends a 20-year, 206 million (1975 $'s) R and D program on geologic structures in the contiguous U.S. and on the midplate Pacific seabed with the objective of developing an acceptable method for disposal of commercial high-level and transuranic wastes by 1997. No differentiation between high-level and transuranic waste disposal is made in the first 5 years of the program. A unique application of probability theory to R and D planning establishes, at a 95% confidence level, that the program objective will be met if at least fifteen generic options and five specific disposal sites are explored in detail and at least two pilot plants are constructed and operated. A parallel effort on analysis and evaluation maximizes information available for decisions on the acceptability of the disposal techniques. Based on considerations of technical feasibility, timing and technical risk, the other disposal concepts, e.g., ice sheets, partitioning, transmutation and space disposal cited in BNWL-1900 are not recommended for near future R and D

Scenarios of the TWRS low-level waste disposal program

International Nuclear Information System (INIS)

1994-10-01

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 Area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pretreating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste

Decision nearing on final disposal of spent fuel in Finland

International Nuclear Information System (INIS)

Vira, J.

2000-01-01

The programme for final disposal of spent fuel from Finnish nuclear power plants is entering into important phase: in the year 2000 the Finnish Government is expected to decide whether the proposal made by Posiva Oy on the spent fuel disposal is in line with the overall good of society. Associated with the decision is also Posiva's proposal on siting the disposal facility at Olkiluoto in Eurajoki municipality on the western coast of Finland. An important document underlying Posiva's application for this principle decision is the report of the environmental impact assessment, which was completed in 1999. Safety considerations play an important role in the application. New assessments have, therefore, been made on both the operational and long-term safety as well as on safety of spent fuel transportation. (author)

Validation and application of help code used for design and review of cover of low and intermediate level radioactive waste disposal in near-surface facilities

International Nuclear Information System (INIS)

Fan Zhiwen; Gu Cunli; Zhang Jinsheng; Liu Xiuzhen

1996-01-01

The authors describes validation and application of HELP code used by the United States Environmental Protective Agency for design and review of cover of low and intermediate level radioactive waste disposal in near-surface facilities. The HELP code was validated using data of field aerated moisture movement test by China Institute for Radiation Protection. The results show that simulation of HELP code is reasonable. Effects of surface layer thickness and surface treatment on moisture distribution in a cover was simulated with HELP code in the conditions of south-west China. The simulation results demonstrated that surface plantation of a cover plays very important role in moisture distribution in the cover. Special attention should be paid in cover design. In humid area, radioactive waste disposal safety should take full consideration with functions of chemical barrier. It was recommended that engineering economy should be added in future cover research so as to achieve optimization of cover design

Consideration of post-closure controls for a near surface low level waste disposal site

International Nuclear Information System (INIS)

Clegg, R.; Pinner, A.; Smith, A.; Quartermaine, J.

1997-01-01

There is currently an ongoing programme of disposal of low level radioactive wastes by British Nuclear Fuels plc (BNFL) at Drigg, Cumbria, and this programme is likely to continue through the first few decades of the 21st century. Although control of the site is anticipated for a period of about 100 years post-closure, eventually restrictions on access will lapse. Thereafter, the possibility of human actions leading to exposure to, and/or exhumation of, the wastes exists and has to be addressed in post-closure radiological performance assessments. Potential modes of intrusion into the Drigg site have been studied using a suite of computer codes developed specifically for this purpose. Required inputs to these codes include information on possible future uses of the site and the various human actions associated with those uses. This information was obtained from a group of experts using formal elicitation procedures. Although the most likely site uses, notably those involving agricultural activities, are unlikely to result in intrusion into the wastes, others, such a urban development, do have the potential to result in such intrusion. In these circumstances, it seemed appropriate to give consideration to the degree to which documentary records and markers could protect the Drigg site against intrusive activities. Overall, it is concluded that provided that a variety of documentary records are established, ranging from local council archives to mass produced maps, then memory of the site can realistically be assumed whilst civilization continues to exist. However, if this first line of defence fails, markers constitute a second warning system. Finally, assessment calculations can be used to demonstrate that, even if these two lines of defence fail, risks from intrusion and radiation doses contingent upon intrusive events having occurred would not be unacceptably large. (author). 10 refs, 1 fig., 1 tab

Some legal aspects on high level radioactive waste disposal in Japan

International Nuclear Information System (INIS)

Tanabe, Tomoyuki

1997-01-01

In Japan, it is considered to be an urgent problem to prepare the system for the research and execution of high level radioactive waste disposal. Under what regulation scheme the disposal should be done has not been sufficiently examined. In this research, the examination was carried out on the legal aspects of high level radioactive waste disposal as follows. First, the current legislation on the disposal in Japan was analyzed, and it was made clear that high level radioactive waste disposal has not been stipulated clearly. Next, on the legal choices which are conceivable on the way the legislation for high level radioactive waste disposal should be, from the aspects of applying the law on regulating nuclear reactors and others, applying the law on nuclear power damage reparation, and industrialization by changing the government ordinances, those were arranged in six choices, and the examination was carried out for each choice from the viewpoints of the relation with the base stipulation for waste-burying business, the speciality of high level radioactive waste disposal as compared with other actions of nuclear power business, the coordination with existing nuclear power of nuclear power business, the coordination with existing nuclear power law system and the formation of national consensus. In this research, it was shown that the execution of high level radioactive waste disposal as the business based on the separate legislation is the realistic choice. (K.I.)

Exposure and risk calculations for disposal of wastes having minimal radioactivity

International Nuclear Information System (INIS)

Fields, D.E.

1984-01-01

The US Nuclear Regulatory Commission is currently considering revision of rules 10 CFR 20 and 10 CFR 61, which cover disposal of solid wastes containing minimal activity radioactivity. In support of these revised rules, we have evaluated the consequences of disposing of four waste streams at four types of disposal areas located in three different geographic regions. Consequences are expressed in terms of human exposures and associated health effects. Each geographic region has its own climate and geology. Example waste streams, waste disposal methods, and geographic regions chosen for this study are clearly specified. The PRESTO-II methodology was used to evaluate radionuclide transport and health effects. This methodology was developed to assess radiological impacts to a static local population for a 1000-year period following disposal. The modeling of pathways and processes of migration from the trench to exposed populations included the following considerations: groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. 9 references, 2 figures, 3 tables

Geoenvironment and waste disposal

International Nuclear Information System (INIS)

1983-07-01

Within the activities planned by UNESCO in its Water and Earth Science programme, an interdisciplinary meeting on geology and environment was scheduled by this organization to be held by the beginning of 1983. At this meeting it was intended to consider geological processes in the light of their interaction and influence on the environment with special emphasis on the impact of various means of waste disposal on geological environment and on man-induced changes in the geological environment by mining, human settlements, etc. Considering the increasing interest shown by the IAEA in the field, through environmental studies, site studies, and impact studies for nuclear facilities and particularly nuclear waste disposal, UNESCO expressed the wish to organize the meeting jointly so as to take into account the experience gained by the Agency, and in order to avoid any duplication in the activities of the two organizations. This request was agreed to by the IAEA Secretariat and as a result, the meeting was organized by both organizations and held at IAEA Headquarters in Vienna from 21-23 March 1983. The report of this meeting is herewith presented

Organizing and managing radioactive waste disposal as an experiment

International Nuclear Information System (INIS)

Cook, B.J.; Emel, J.L.; Kasperson, R.E.

1990-01-01

This paper examines organization and management issues engendered by the national program for permanent disposal of commercial radioactive wastes. The description of current organizational and managerial responses to the waste disposal problem serves as a springboard for consideration of the technical, political, and organizational constraints that impinge upon the waste-management effort. Taking these constraints into account, the authors apply ideas that have emerged from previous radioactive waste-management studies and research on organizations, concluding that a change of course is needed. As an alternative, they propose an experimental approach predicated on the waste-management organization's acknowledging uncertainty and constructing responses that seek to reduce uncertainty systematically and without distortion

Key Factors to Determine the Borehole Spacing in a Deep Borehole Disposal for HLW

International Nuclear Information System (INIS)

Lee, Jongyoul; Choi, Heuijoo; Lee, Minsoo; Kim, Geonyoung; Kim, Kyeongsoo

2015-01-01

Deep fluids also resist vertical movement because they are density stratified and reducing conditions will sharply limit solubility of most dose critical radionuclides at the depth. Finally, high ionic strengths of deep fluids will prevent colloidal transport. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept for deep borehole disposal of spent fuels or high level radioactive wastes which has been developed by some countries according to the rapid advance in the development of drilling technology, as an alternative method to the deep geological disposal method, was reviewed. After then an analysis on key factors for the distance between boreholes for the disposal of HLW was carried out. In this paper, the general concept for deep borehole disposal of spent fuels or HLW wastes, as an alternative method to the deep geological disposal method, were reviewed. After then an analysis on key factors for the determining the distance between boreholes for the disposal of HLW was carried out. These results can be used for the development of the HLW deep borehole disposal system

Key Factors to Determine the Borehole Spacing in a Deep Borehole Disposal for HLW

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-15

Deep fluids also resist vertical movement because they are density stratified and reducing conditions will sharply limit solubility of most dose critical radionuclides at the depth. Finally, high ionic strengths of deep fluids will prevent colloidal transport. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept for deep borehole disposal of spent fuels or high level radioactive wastes which has been developed by some countries according to the rapid advance in the development of drilling technology, as an alternative method to the deep geological disposal method, was reviewed. After then an analysis on key factors for the distance between boreholes for the disposal of HLW was carried out. In this paper, the general concept for deep borehole disposal of spent fuels or HLW wastes, as an alternative method to the deep geological disposal method, were reviewed. After then an analysis on key factors for the determining the distance between boreholes for the disposal of HLW was carried out. These results can be used for the development of the HLW deep borehole disposal system.

Language Interpretation for Diverse Families: Considerations for Special Education Teachers

Science.gov (United States)

More, Cori M.; Hart, Juliet E.; Cheatham, Gregory A.

2013-01-01

The special education field is challenged by a lack of attention to and recruitment of well-trained language interpreters in schools. As such, special education teachers need to take a leadership role in working with interpreters to ensure diverse families are collaborative members of individualized education program (IEP) teams. Using the…

Concept and programme open-quotes Radioactive waste disposal in geological formations of Ukraineclose quotes

International Nuclear Information System (INIS)

Khrushchov, D.P.; Umanets, M.P.; Yakovlev, Eu.A.

1994-01-01

The concept and the programme open-quotes Radioactive waste disposal in geological formations of Ukraineclose quotes have been compiled. On the base of specialized criterions the evaluation of the territory of Ukraine was carried out, three geological regions and three types of geological formations favourable for RAW disposal have been selected. The programme of R ampersand D investigations includes three stages: preparatory (1993-1995), preparatory - experimental (1995-2004) and preparation of construction (2005-2010)

40 CFR 264.312 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

..., AND DISPOSAL FACILITIES Landfills § 264.312 Special requirements for ignitable or reactive waste. (a... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 264.312 Section 264.312 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

40 CFR 265.256 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

... TREATMENT, STORAGE, AND DISPOSAL FACILITIES Waste Piles § 265.256 Special requirements for ignitable or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 265.256 Section 265.256 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

40 CFR 264.281 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

..., AND DISPOSAL FACILITIES Land Treatment § 264.281 Special requirements for ignitable or reactive waste... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 264.281 Section 264.281 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

40 CFR 264.256 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

..., AND DISPOSAL FACILITIES Waste Piles § 264.256 Special requirements for ignitable or reactive waste... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 264.256 Section 264.256 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

Waste Management, Treatment, and Disposal for the Food Processing Industry. Special Circular 113.

Science.gov (United States)

Wooding, N. Henry

This publication contains information relating to waste prevention, treatment and disposal, and waste product utilization. Its primary purpose is to provide information that will help the food industry executive recognize waste problems and make wise management decisions. The discussion of the methods, techniques, and the state-of-the-art is…

Disposal of the radioactive contaminated soils from the NPP site

International Nuclear Information System (INIS)

Matusek, I.; Plsko, J.; Sajtlava, M.; Hulla, J.; Kovacs, T.

2004-01-01

Disposal of contaminated soils at site of NPP is one of the most important task within the frame of research and development tasks of the NPP decommissioning. The works within this field can be seen in several areas. Considered soil activity monitoring, observation of its geo-technical and geo-chemical parameters, volume balance, research of the radio nuclides behaviour in the soil and simulation of their influence on the surrounding environment with special emphasis on underground water, project studies and construction of the disposal facility for contaminated soils. This work presents overview of gained results in the mentioned areas of the research and development. (author)

Basic research needs for management and disposal of DOE wastes

International Nuclear Information System (INIS)

Grazis, B.M.; Schulz, W.W.

1991-04-01

This document was chartered by the Department of Energy (DOE), Office of Energy Research. It identifies and describes 87 basic research needs in support of advanced technology for management and disposal of Department of Energy radioactive, hazardous chemical, and mixed wastes. A team of scientists and engineers from several DOE laboratories and sites, from academia, and from industry identified and described the basic research needs called out in this report. Special efforts were made to ensure that basic research needs related to management and disposal of any hazardous chemical wastes generated at nonnuclear DOE sites and facilities were properly identified. It is hoped that scientists in both DOE and nongovernment laboratories and institutions will find this document useful when formulating research efforts relevant to waste management and disposal. For management and disposal of DOE radioactive and mixed wastes, basic research needs are identified in nine separate action areas. Basic research needs for management and disposal of DOE hazardous chemical wastes are identified in five action areas. Sufficient description and background information are provided in the report for each particular research need to enable qualified and imaginative scientists to conceive research efforts and programs that will meet the need. 28 refs., 7 tabs

Analyses of the deep borehole drilling status for a deep borehole disposal system

Energy Technology Data Exchange (ETDEWEB)

Lee, Jong Youl; Choi, Heui Joo; Lee, Min Soo; Kim, Geon Young; Kim, Kyung Su [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The purpose of disposal for radioactive wastes is not only to isolate them from humans, but also to inhibit leakage of any radioactive materials into the accessible environment. Because of the extremely high level and long-time scale radioactivity of HLW(High-level radioactive waste), a mined deep geological disposal concept, the disposal depth is about 500 m below ground, is considered as the safest method to isolate the spent fuels or high-level radioactive waste from the human environment with the best available technology at present time. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general status of deep drilling technologies was reviewed for deep borehole disposal of high level radioactive wastes. Based on the results of these review, very preliminary applicability of deep drilling technology for deep borehole disposal analyzed. In this paper, as one of key technologies of deep borehole disposal system, the general status of deep drilling technologies in oil industry, geothermal industry and geo scientific field was reviewed for deep borehole disposal of high level radioactive wastes. Based on the results of these review, the very preliminary applicability of deep drilling technology for deep borehole disposal such as relation between depth and diameter, drilling time and feasibility classification was analyzed.

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...

Verification of Sulfate Attack Penetration Rates for Saltstone Disposal Unit Modeling

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-12

Recent Special Analysis modeling of Saltstone Disposal Units consider sulfate attack on concrete and utilize degradation rates estimated from Cementitious Barriers Partnership software simulations. This study provides an independent verification of those simulation results using an alternative analysis method and an independent characterization data source. The sulfate penetration depths estimated herein are similar to the best-estimate values in SRNL-STI-2013-00118 Rev. 2 and well below the nominal values subsequently used to define Saltstone Special Analysis base cases.

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.

The effects of actinide separation on the radiological consequences of geologic disposal of high-level waste

International Nuclear Information System (INIS)

Hill, M.D.; White, I.F.; Fleishman, A.B.

1980-01-01

It has often been suggested that the potential hazard to man from the disposal of high-level radioactive waste could be reduced by removing a substantial fraction of the actinide elements. In this report the effects of actinide separation on the radiological consequences of one of the disposal options currently under consideration, that of burial in deep geologic formations, are examined. The results show that the potential radiological impact of geologic disposal of high-level waste arises from both long-lived fission products and actinides (and their daughter radionuclides). Neither class of radionuclides is of overriding importance and actinide separation would therefore reduce the radiological impact to only a limited extent and over limited periods. There might be a case for attempting to reduce doses from 237 Np. To achieve this it appears to be necessary to separate both neptunium and its precursor element americium. However, there are major uncertainties in the data needed to predict doses from 237 Np; further research is required to resolve these uncertainties. In addition, consideration should be given to alternative methods of reducing the radiological impact of geologic disposal. The conclusions of this assessment differ considerably from those of similar studies based on the concept of toxicity indices. Use of these indices can lead to incorrect allocation of research and development effort. (author)

Experience of NS disposal at the Enterprise ''Zvezdochka'', in Severodvinsk. Problems of ecological safety

International Nuclear Information System (INIS)

Kozlov, Yuri

1999-01-01

According to this presentation, decommissioning and disposal of nuclear submarines is a problem of great concern in Russia. So far more than 150 nuclear submarines have been removed from the Fleet and will be disposed of. Future disposals were not taken into consideration when the shipyards were constructed. Nuclear vessels with loaded cores stay afloat waiting for their turn to be disposed of, often with damaged safety assurance systems and a potential for causing major ecological catastrophes. The presentation deals briefly with some international programmes in progress at Nerpa in Murmansk, Zvezda in Primorye and Zvezdochka in Arkhangelsk and then discusses in more detail the experience of disposal at the Zvezdochka, which under the Start-2 agreement is defined as one of the enterprises dealing with the disposal of strategic nuclear submarines. There they have the qualified staff and the equipment needed. Spent nuclear fuel unloading and removal is the most acute problem

26 CFR 301.7326-1 - Disposal of forfeited or abandoned property in special cases.

Science.gov (United States)

2010-04-01

... narcotic drugs, see 21 CFR 302.56. For the disposal of forfeited marihuana, see 26 CFR (1939) 152.99 and 152.100 (Regulations under the Marihuana Tax Act of 1937, as amended). (c) Firearms. For regulations...

Studies involving proposed waste disposal facilities in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1987-01-01

The Turkish government is in the process of planning two nuclear reactors in Turkey. The Turkish Atomic Energy Authority has been given the task of developing plans for improved control of low-level wastes (LLW) in Turkey. Principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries, and two research reactors in Turkey. These wastes will be treated in a pilot water treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200-l concrete containers until the establishment of the permanent waste disposal sites in Turkey in 1990. The PRESTO-II (prediction of radiation effects from shallow trench operations) computer code has been applied for the general probable sites for LLW disposal in Turkey. The model is intended to serve as a non-site-specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this code takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides, and use of this contaminated ground water for farming, irrigation, and ingestion

High activity waste disposal

International Nuclear Information System (INIS)

Gaul, W.C.

1990-01-01

Chem-Nuclear Environmental Services (CNES) has developed a container that is capable of containing high activity waste and can be shipped as a regular DOT Type A shipment. By making the container special form the amount of activity that can be transported in a Type A shipment is greatly enhanced. Special form material presents an extra degree of protection to the environment by requiring the package to be destroyed to get access to the radioactive material and must undergo specific testing requirements, whereas normal form material can allow access to the radioactive material. With the special form container up to 10 caries of radium can be transported in a single package. This paper will describe the considerations that were taken to develop these products

Experiences and history of the spent fuel disposal programme in Finland

International Nuclear Information System (INIS)

Wang Ju

2004-01-01

This paper briefly introduces the Finnish geological disposal programme for spent fuel, including the management structure, technical strategy for R and D, history of R and D, technical considerations, siting process, site characterization, underground research laboratory development and its successful experiences. (author)

US DOE-EM On-Site Disposal Cell Working Group - Fostering Communication On Performance Assessment Challenges

Energy Technology Data Exchange (ETDEWEB)

Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States); Suttora, Linda C. [U.S. Department of Energy, Office of Site Restoration, Germantown, MD (United States); Phifer, Mark [Savannah River Site (SRS), Aiken, SC (United States)

2014-03-01

On-site disposal cells are in use and being considered at several U.S. Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These facilities are typically developed with regulatory oversight from States and/or the US Environmental Protection Agency (USEPA) in addition to USDOE. The facilities are developed to meet design standards for disposal of hazardous waste as well as the USDOE performance based standards for disposal of radioactive waste. The involvement of multiple and different regulators for facilities across separate sites has resulted in some differences in expectations for performance assessments and risk assessments (PA/RA) that are developed for the disposal facilities. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. The working group holds teleconferences, as needed, focusing on specific topics of interest. The topics addressed to date include an assessment of the assumptions used for performance assessments and risk assessments (PA/RAs) for on-site disposal cells, requirements and assumptions related to assessment of inadvertent intrusion, DOE Manual 435.1-1 requirements, and approaches for consideration of the long-term performance of liners and covers in the context of PAs. The working group has improved communication among the staff and oversight personnel responsible for onsite disposal cells and has provided a forum to identify and resolve common concerns.

Unrestricted disposal of minimal activity levels of radioactive wastes: exposure and risk calculations

International Nuclear Information System (INIS)

Fields, D.E.; Emerson, C.J.

1984-08-01

The US Nuclear Regulatory Commission is currently considering revision of rule 10 CFR Part 20, which covers disposal of solid wastes containing minimal radioactivity. In support of these revised rules, we have evaluated the consequences of disposing of four waste streams at four types of disposal areas located in three different geographic regions. Consequences are expressed in terms of human exposures and associated health effects. Each geographic region has its own climate and geology. Example waste streams, waste disposal methods, and geographic regions chosen for this study are clearly specified. Monetary consequences of minimal activity waste disposal are briefly discussed. The PRESTO methodology was used to evaluate radionuclide transport and health effects. This methodology was developed to assess radiological impacts to a static local population for a 1000-year period following disposal. Pathways and processes of transit from the trench to exposed populations included the following considerations: groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. 12 references, 2 figures, 8 tables

Application of Bayesian network to the probabilistic risk assessment of nuclear waste disposal

International Nuclear Information System (INIS)

Lee, Chang-Ju; Lee, Kun Jai

2006-01-01

The scenario in a risk analysis can be defined as the propagating feature of specific initiating event which can go to a wide range of undesirable consequences. If we take various scenarios into consideration, the risk analysis becomes more complex than do without them. A lot of risk analyses have been performed to actually estimate a risk profile under both uncertain future states of hazard sources and undesirable scenarios. Unfortunately, in case of considering specific systems such as a radioactive waste disposal facility, since the behaviour of future scenarios is hardly predicted without special reasoning process, we cannot estimate their risk only with a traditional risk analysis methodology. Moreover, we believe that the sources of uncertainty at future states can be reduced pertinently by setting up dependency relationships interrelating geological, hydrological, and ecological aspects of the site with all the scenarios. It is then required current methodology of uncertainty analysis of the waste disposal facility be revisited under this belief. In order to consider the effects predicting from an evolution of environmental conditions of waste disposal facilities, this paper proposes a quantitative assessment framework integrating the inference process of Bayesian network to the traditional probabilistic risk analysis. We developed and verified an approximate probabilistic inference program for the specific Bayesian network using a bounded-variance likelihood weighting algorithm. Ultimately, specific models, including a model for uncertainty propagation of relevant parameters were developed with a comparison of variable-specific effects due to the occurrence of diverse altered evolution scenarios (AESs). After providing supporting information to get a variety of quantitative expectations about the dependency relationship between domain variables and AESs, we could connect the results of probabilistic inference from the Bayesian network with the consequence

Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2013-01-31

The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of

Criteria for long-term hazard assessment of chemotoxic and radiotoxic waste disposal

International Nuclear Information System (INIS)

Merz, E.R.

1988-01-01

Present-day human activities generate chemotoxic as well as radiotoxic wastes. They must likewise be considered as extremely hazardous. If wastes are composed simultaneously of both kinds, as may occur in nuclear facility operations or nuclear medical applications, the material is called mixed waste. Whereas radioactive waste management and disposal have received considerable attention in the past, less care has been devoted to chemotoxic wastes. Also, mixed wastes may pose problems diverging from singly composed materials. The disposal of mixed wastes is not sufficiently well regulated in the Federal Republic of Germany. Currently, non-radioactive hazardous wastes are mostly disposed of by shallow land burial. Much more rigorous safety precautions are applied with regard to radioactive wastes. According to the orders of the German Federal Government, their disposal is only permitted in continental underground repositories. These repository requirements for radioactive waste disposal should be superior to the near-surface disposal facilities. At present, federal and state legislation do not permit hazardous chemical and radioactive wastes to be deposited simultaneously. It is doubtful whether this instruction is always suitable and also justified. This paper presents a modified strategy

Offsite source recovery project - ten years of sealed source recovery and disposal

Energy Technology Data Exchange (ETDEWEB)

Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA

2010-01-01

The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources (this number has since increased to more than 23,000). This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Decades later, these sources began to exceed their special form certifications or fall out of regular use. As OSRP has collected and stored sealed sources, initially using 'No Path Forward' waste exemptions for storage within the Department of Energy (DOE) complex, it has consistently worked to create disposal pathways for the material it has recovered. The project was initially restricted to recovering sealed sources that would meet the definition of Greater-than-Class-C (GTCC) low-level radioactive waste, assisting DOE in meeting its obligations under the Low-level Radioactive Waste Policy Act Amendments (PL 99-240) to provide disposal for this type of waste. After being transferred from DOE-Environmental Management (EM) to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as GTCC when it became waste, but also any other materials that might constitute a 'national security consideration.' It was recognized at the time that the GTCC category was a waste designation having to do with environmental consequence, rather than the threat posed by deliberate or accidental misuse. The project faces barriers to recovery in many areas, but disposal continues to be one of the more difficult to overcome. This paper discusses OSRP's disposal efforts over its 10-year history. For sources

Unused Medications Disposal Practice: The case of Patients Visiting University of Gondar Specialized Teaching Hospital, Gondar, Ethiopia

OpenAIRE

Tadele Atinafu; Abayneh Takele; Adeladlew Kassie; Adane Yehualaw; Getu Tesfaw; Tesfanesh Desseno; Tadesse Mekonnen; Mulugeta Fentie

2014-01-01

Background: The disposal of unwanted medications has been a concern in many countries, as pharmaceutical waste enters the ecosystem, ultimately having an effect on human health and environment. The main objective of this study was to assess unused medications disposal practice of patients Method: Institution based cross sectional study was used. Patients were systematically selected and interviewed using structured questionnaires. The Data was analyzed using SPSS version 20. Result: Out of...

Consideration of liners and covers in performance assessments

Energy Technology Data Exchange (ETDEWEB)

Phifer, Mark A. [Savannah River National Laboratory, Aiken, SC (United States); Seitz, Robert R. [Savannah River National Laboratory, Aiken, SC (United States); Suttora, Linda C. [USDOE Enviromental Management, Washington, DC (United States)

2014-09-18

On-site disposal cells are in use and being considered at several United States Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These disposal cells are typically regulated by States and/or the U.S. Environmental Protection Agency under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management due to the radioactive waste. The USDOE-Environmental Management Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these CERCLA disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to CERCLA risk assessments and DOE Order 435.1 performance assessments in support of a Record of Decision and Disposal Authorization Statement, respectively. One of the issues considered by the working group, which is addressed in this report, was how to appropriately consider the performance of covers and liners/leachate collections systems in the context of a DOE Order 435.1 performance assessment (PA). This same information may be appropriate for consideration within CERCLA risk assessments for these facilities. These OSDCs are generally developed to meet hazardous waste (HW) disposal design standards under the Resource Conservation and Recovery Act (RCRA) as well as the DOE Order 435.1 performance based standards for disposal of radioactive waste. To meet the standards for HW, the facilities typically include engineered covers and liner/leachate collection systems. Thus, when considering such facilities in the context of a DOE Order 435.1 PA, there is a need to address the evolution of performance of covers and liner/leachate collection systems in the context of meeting a performance standard considering time

Nuclear fuel waste disposal. Canada's consultative approach

International Nuclear Information System (INIS)

Hillier, J.A.R.; Dixon, R.S.

1993-01-01

Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

Nuclear fuel waste disposal. Canada's consultative approach

Energy Technology Data Exchange (ETDEWEB)

Hillier, J A.R.; Dixon, R S [AECL (Canada)

1993-07-01

Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

The geochemical environment of nuclear fuel waste disposal

International Nuclear Information System (INIS)

Gascoyne, M.

1995-01-01

The concept for disposal of Canada's nuclear fuel waste in a geologic environment on the Canadian Shield has recently been presented by Atomic Energy of Canada Limited (AECL) to governments, scientists, and the public, for review. An important part of this concept concerns the geochemical environment of a disposal vault and includes consideration of rock and groundwater compositions, geochemical interactions between rocks, groundwaters, and emplaced vault materials, and the influences and significance of anthropogenic and microbiological effects following closure of the vault. This paper summarizes the disposal concept and examines aspects of the geochemical environment. The presence of saline groundwaters and reducing conditions at proposed vault depths (500-1000 m) in the Canadian Shield has an important bearing on the stability of the used nuclear fuel, its container, and buffer and backfill materials. The potential for introduction of anthropogenic contaminants and microbes during site investigations and vault excavation, operation, and sealing is described with examples from AECL's research areas on the Shield and in their underground research laboratory in southeastern Manitoba. (author)

7 CFR 1951.241 - Special provision for interest rate change.

Science.gov (United States)

2010-01-01

... 7 Agriculture 14 2010-01-01 2009-01-01 true Special provision for interest rate change. 1951.241... Community and Direct Business Programs Loans and Grants § 1951.241 Special provision for interest rate... interest rate charged by FmHA or its successor agency under Public Law 103-354 to water and waste disposal...

Low level waste disposal regulatory issues in the US - 59311

International Nuclear Information System (INIS)

James, David; Kalinowski, Thomas; Edwards, Lisa

2012-01-01

Document available in abstract form only. Full text of publication follows: The United States led the international efforts to define disposal requirements for low level radioactive wastes with the publication of US Regulations governing the disposal of such wastes. The requirements were based on a system of waste classification based on the concentrations of certain radionuclides considered problematic for the protection of future generations from radiation exposure. The regulation, itself, was based on a process for the development of new disposal sites defined by the US congress to provide an equitable distribution of burden to various regions of the US. This process has met with little success in the almost 30 years since its initiation leaving only an incomplete patchwork of disposal options which are primarily dependant on the same options that existed before the act and regulations were initiated. There is currently a new focus on the basis for some of the regulatory requirements derived from advances in the understanding of dose impacts from certain radionuclides, improvements in performance assessment methodologies, the increased use of engineered barriers, the reality of current disposal economies, along with the failure of the act to conform to expectations. This paper will provide an update on the discussion taking place with a focus on the technical considerations. (authors)

Disposal of waste by hydraulic fracturing

International Nuclear Information System (INIS)

Tamura, T.; Weeren, H.

1984-01-01

Liquid radioactive waste solutions at the Oak Ridge National Laboratory (ORNL) have been disposed of for nearly 20 years by preparing a slurry, injecting it into bedding plane fractures formed in low-permeability shale, and allowing the slurry to set into a solid. Three major considerations are required for this method: a rock formation that forms horizontal or bedding plane fractures and is highly impermeable, a plant facility that can develop sufficient hydraulic pressure to fracture the rock and to inject the slurry, and a slurry that can be pumped into the fracture and that will set, preferably, into a low-leaching solid. The requirements and desirable conditions of the formation, the process and facility as used for radioactive waste disposal, and the mix formulation and slurry properties that were required for injection and solidification are described. The intent of this paper is to stimulate interest in this technique for possible application to nonnuclear wastes

Special barium-lead mortars for radioactive wastes sealing and insulation

International Nuclear Information System (INIS)

Usai, G.

1995-01-01

Binding materials with high gamma-absorbance, easy to prepare and use, are of great usefulness in the elimination and disposal of low-level radioactive wastes such as clinical wastes. Use of these materials ranges from construction of containers to sealing of vessels designed for wastes disposal. In this paper the authors describe preparation of special mortars containing barite and/or PbO characterized by good hydraulic properties and high insulating power

Disposal of spent fuel from German nuclear power plants - paper work or technology?

International Nuclear Information System (INIS)

Graf, R.; Filbert, W.

2006-01-01

The reference concept 'direct disposal of spent fuel' was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this reference concept - the so called POLLUX-concept, e.g. interim storages for casks containing spent fuel, a pilot conditioning facility, and a special cask 'POLLUX' for final disposal have been built. With view to a geological salt formation all handling procedures for the repository were tested aboveground in a test facility at a 1:1 scale. To optimise the concept all operational steps are reviewed for possible improvement. Most promising are a concept using canisters (BSK 3) instead of POLLUX casks, and the direct disposal of transport and storage casks (DIREGT-concept) which is the most recent one and has been designed for the direct disposal of large transport and storage casks. The final exploration of the pre-selected repository site is still pending, from the industries point of view due to political reasons only. The present paper describes the main concepts and their status as of today. (author)

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)

Comparison of potential health and safety impacts of different disposal options for defense high-level wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Smith, E.D.; Witherspoon, J.P.

1984-01-01

A comparative assessment has been performed of the potential long- and short-term health and safety impacts of different disposal options for defense high-level wastes. Conservative models and assumptions were used. The assessment suggests that considerations of health and safety will not be significant in choosing among disposal options, primarily because of the need to meet stringent standards in all cases. Rather, the ease and cost of assuring compliance of a particular disposal option with health and safety standards may be a more important factor. 11 references

An investigation of storage and treatment options for radioactive wastes prepared for sea disposal

International Nuclear Information System (INIS)

Wakerley, M.W.; Woodfine, B.C.

1986-07-01

A sea disposal of 3500 t of packaged waste using a specially converted ship was planned for 1983, but did not take place. The major part of this waste is currently stored at two UKAEA sites. The waste packages were made with the intention that they would be disposed of within about 18 months of packaging. It was not intended that they would be stored for long periods. All wastes are packaged in mild steel drums and the wastes are temporarily stored within buildings. The conditions under which the packages are stored and their present condition are described and possible storage and treatment options are investigated having regard to available disposal routes. (author)

Proposal for a research programme on geological disposal of radioactive waste in the Netherlands

International Nuclear Information System (INIS)

1984-06-01

The present report sets out a tentative research program related to radiologic safety of geological disposal of radioactive waste, set against the background of present knowledge in this field. The final stage of this program has to lead to a definitive appraisal of the suitability of the site explored in that stage for disposal of high-level radioactive waste. Subsequent stages of the research effort is outlined in a critical path diagram. Radiological safety figures as the central factor in making choices. The report indicates the state of the art in different specialisms involved in the study of both natural barriers (rheology, hydrology, radionuclide transport, radiation damage) and artificial barriers (mining engineering) for geological disposal. (G.J.P.)

Reduction of greenhouse gas emissions in the rape cultivation with special consideration of nitrogen fertilization

International Nuclear Information System (INIS)

Heilmann, Hubert; Riemer, Doerte

2017-01-01

Involved into the research project ''Mitigation of greenhouse gas emissions in oilseed rape cropping with special consideration of nitrogen fertilizing'' regional specific GHG cropping emissions according to benchmark and regional experts are calculated by using a calculation method developed in cooperation with IFEU and according to IPCC (2006). The following results are achieved for 35 German NUTS2-regions: - nitrogen fertilization is the main influence for GHG emission reduction; - the use of low-emission nitrogen fertilizers is worth for GHG emission reduction; - without increasing the nutrient efficiency of organic fertilizers, GHG emission reductions are difficult to achieve in many regions; - GHG emission reduction/climate protection and realization of the WRRL or N-Saldo reduction come up to the same aim; - economic consequences of restrictive carbon mitigation can be compensated by slight price surcharges for certified raw material.

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

40 CFR 503.11 - Special definitions.

Science.gov (United States)

2010-07-01

... land with indigenous vegetation. (n) Reclamation site is drastically disturbed land that is reclaimed... FOR THE USE OR DISPOSAL OF SEWAGE SLUDGE Land Application § 503.11 Special definitions. (a) Agricultural land is land on which a food crop, a feed crop, or a fiber crop is grown. This includes range land...

Treatment and disposal of tyres: Two EU approaches. A review.

Science.gov (United States)

Torretta, Vincenzo; Rada, Elena Cristina; Ragazzi, Marco; Trulli, Ettore; Istrate, Irina Aura; Cioca, Lucian Ionel

2015-11-01

The treatment and disposal of tyres from vehicles has long been of considerable environmental importance. The main problem lies in the mixed composition of the tyres. Studies have been undertaken to modify the structure of the tyres, especially with reference to the percentage of granulated rubber incorporated, in order to improve their performance, and also to reduce their environmental impact during normal functioning (noise, particulates, etc.) and facilitate recycling and final disposal. The aim of the present study is to review and compare how used tyres are treated and disposed of in two different EU countries. The first is Italy, which has been part of the European Union since its inception, and has important industrial traditions. The second is Romania, an emerging country which recently became part of the EU, and whose economic and industrial development has had a major boost in recent years, with a strong growth in waste production, together with consumption in urban areas. The occasion was useful to consider the situation concerning the evolution of the different aspects related to the management of the end-of-life tyres. In particular, the paper considers the properties of tyre waste and their potential reuse, the enhancement of end-of-life tires and the various types of recovery, such as the reconstruction of tyres and the material recovery. The aspects related to the energy recovery and the use of the life cycle analysis, as a tool to support the choices of the best management system, were also taken into consideration, not forgetting that an adequate end-of-life planning is important when developing a sustainable product, since it can affect considerably its overall life cycle. Copyright © 2015 Elsevier Ltd. All rights reserved.

Geomechanical Considerations for the Deep Borehole Field Test

Science.gov (United States)

Park, B. Y.

2015-12-01

Deep borehole disposal of high-level radioactive waste is under consideration as a potential alternative to shallower mined repositories. The disposal concept consists of drilling a borehole into crystalline basement rocks to a depth of 5 km, emplacement of canisters containing solid waste in the lower 2 km, and plugging and sealing the upper 3 km of the borehole. Crystalline rocks such as granites are particularly attractive for borehole emplacement because of their low permeability and porosity at depth, and high mechanical strength to resist borehole deformation. In addition, high overburden pressures contribute to sealing of some of the fractures that provide transport pathways. We present geomechanical considerations during construction (e.g., borehole breakouts, disturbed rock zone development, and creep closure), relevant to both the smaller-diameter characterization borehole (8.5") and the larger-diameter field test borehole (17"). Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

Assessment of alternative disposal methods to reduce greenhouse gas emissions from municipal solid waste in India.

Science.gov (United States)

Yedla, Sudhakar; Sindhu, N T

2016-06-01

Open dumping, the most commonly practiced method of solid waste disposal in Indian cities, creates serious environment and economic challenges, and also contributes significantly to greenhouse gas emissions. The present article attempts to analyse and identify economically effective ways to reduce greenhouse gas emissions from municipal solid waste. The article looks at the selection of appropriate methods for the control of methane emissions. Multivariate functional models are presented, based on theoretical considerations as well as the field measurements to forecast the greenhouse gas mitigation potential for all the methodologies under consideration. Economic feasibility is tested by calculating the unit cost of waste disposal for the respective disposal process. The purpose-built landfill system proposed by Yedla and Parikh has shown promise in controlling greenhouse gas and saving land. However, these studies show that aerobic composting offers the optimal method, both in terms of controlling greenhouse gas emissions and reducing costs, mainly by requiring less land than other methods. © The Author(s) 2016.

Alternate Methods of Effluent Disposal for On-Lot Home Sewage Systems. Special Circular 214.

Science.gov (United States)

Wooding, N. Henry

This circular provides current information for homeowners who must repair or replace existing on-lot sewage disposal systems. Several alternatives such as elevated sand mounds, sand-lined beds and trenches and oversized absorption areas are discussed. Site characteristics and preparation are outlined. Each alternative is accompanied by a diagram…

Alternative disposal options for transuranic waste

International Nuclear Information System (INIS)

Loomis, G.G.

1994-01-01

Three alternative concepts are proposed for the final disposal of stored and retrieved buried transuranic waste. These proposed options answer criticisms of the existing U.S. Department of Energy strategy of directly disposing of stored transuranic waste in deep, geological salt formations at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The first option involves enhanced stabilization of stored waste by thermal treatment followed by convoy transportation and internment in the existing WIPP facility. This concept could also be extended to retrieved buried waste with proper permitting. The second option involves in-state, in situ internment using an encapsulating lens around the waste. This concept applies only to previously buried transuranic waste. The third option involves sending stored and retrieved waste to the Nevada Test Site and configuring the waste around a thermonuclear device from the U.S. or Russian arsenal in a specially designed underground chamber. The thermonuclear explosion would transmute plutonium and disassociate hazardous materials while entombing the waste in a national sacrifice area

Performance assessment review for DOE LLW disposal facilities

International Nuclear Information System (INIS)

Wilhite, Elmer L.

1992-01-01

The United States Department of Energy (US DOE) disposes of low-level radioactive waste in near-surface disposal facilities. Safety of the disposal operations is evaluated for operational safety as well as long-term safety. Operational safety is evaluated based on the perceived level of hazard of the operation and may vary from a simple safety assessment to a safety analysis report. Long-term safety of all low-level waste disposal systems is evaluated through the conduct of a radiological performance assessment. The US DOE has established radiological performance objectives for disposal of low-level waste. They are to protect a member of the general public from receiving over 25 mrem/y, and an inadvertent intruder into the waste from receiving over 100 mrem/y continuous exposure or 500 mrem from a single exposure. For a disposal system to be acceptable, a performance assessment must be prepared which must be technically accurate and provide reasonable assurance that these performance objectives are met. Technical quality of the performance assessments is reviewed by a panel of experts. The panel of experts is used in two ways to assure the technical quality of performance assessment. A preliminary (generally 2 day) review by the panel is employed in the late stages of development to provide guidance on finalizing the performance assessment. The comments from this review are communicated to the personnel responsible for the performance assessment for consideration and incorporation. After finalizing the performance assessment, it is submitted for a formal review. The formal review is accomplished by a much more thorough analysis of the performance assessment over a multi-week time period. The panel then formally reports their recommendations to the US DOE waste management senior staff who make the final determination on acceptability of the performance assessment. A number of lessons have been learned from conducting several preliminary reviews of performance

40 CFR 268.9 - Special rules regarding wastes that exhibit a characteristic.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Special rules regarding wastes that... (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS General § 268.9 Special rules regarding wastes that exhibit a characteristic. (a) The initial generator of a solid waste must determine each EPA...

New safety concept for geological disposal in Japan - -16339

International Nuclear Information System (INIS)

Kitayama, Kazumi

2009-01-01

This paper describes a new safety concept for the Japanese geological disposal program, which is a development of the conventional multi-barrier system concept. The Japanese government established the 'Nuclear Waste Management Organization of Japan' (NUMO) as an implementation body in 2000 based on the 'Final disposal act' following the publication of the 'H-12 Report', which confirmed the scientific and engineering feasibility of HLW geological disposal in Japan. Since then, NUMO has undertaken further technical developments aimed at achieving safe and efficient implementation of final disposal. The safety concept developed in the 'H-12 Report' provides sufficient safety on the basis of site-generic considerations. However, it is considered to be over-conservative and therefore does not represent the most probable performance of the engineered or natural barriers. Recently, concrete measures have been proposed requiring the safety case to be presented in terms of a realistic assessment of the most probable performance. This approach takes into account the safety functions of both engineered and natural barriers as well as the long-term static geochemical equilibrium. In particular, the evolution of the safety performance of engineered and natural barriers can be efficiently augmented by the realistic long-term geochemical equilibrium. (author)

Radioactive mixed waste disposal

International Nuclear Information System (INIS)

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

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

Scenarios of the TWRS low-level waste disposal program. Revision 1

International Nuclear Information System (INIS)

1995-01-01

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pre-treating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste

The effect of food waste disposers on municipal waste and wastewater management.

Science.gov (United States)

Marashlian, Natasha; El-Fadel, Mutasem

2005-02-01

This paper examines the feasibility of introducing food waste disposers as a waste minimization option within urban waste management schemes, taking the Greater Beirut Area (GBA) as a case study. For this purpose, the operational and economic impacts of food disposers on the solid waste and wastewater streams are assessed. The integration of food waste disposers can reduce the total solid waste to be managed by 12 to 43% under market penetration ranging between 25 and 75%, respectively. While the increase in domestic water consumption (for food grinding) and corresponding increase in wastewater flow rates are relatively insignificant, wastewater loadings increased by 17 to 62% (BOD) and 1.9 to 7.1% (SS). The net economic benefit of introducing food disposers into the waste and wastewater management systems constitutes 7.2 to 44.0% of the existing solid waste management cost under the various scenarios examined. Concerns about increased sludge generation persist and its potential environmental and economic implications may differ with location and therefore area-specific characteristics must be taken into consideration when contemplating the adoption of a strategy to integrate food waste disposers in the waste-wastewater management system.

Benefit-cost-risk analysis of alternatives for greater-confinement disposal of radioactive waste

International Nuclear Information System (INIS)

Gilbert, T.L.; Luner, C.; Peterson, J.M.

1983-01-01

Seven alternatives are included in the analysis: near-surface disposal; improved waste form; below-ground engineered structure; augered shaft; shale fracturing; shallow geologic repository; and high-level waste repository. These alternatives are representative generic facilities that span the range from low-level waste disposal practice to high-level waste disposal practice, tentatively ordered according to an expected increasing cost and/or effectiveness of confinement. They have been chosen to enable an assessment of the degree of confinement that represents an appropriate balance between public health and safety requirements and costs rather than identification of a specific preferred facility design. The objective of the analysis is to provide a comparative ranking of the alternatives on the basis of benefit-cost-risk considerations

Radioactive waste sea disposal practices and the need for international regulations

International Nuclear Information System (INIS)

Reyners, P.

1975-01-01

Radioactive waste is mainly disposed of as liquid releases in coastal waters or as solid wastes dumped in the high seas. The Geneva Convention on the high seas which lays down that Contracting States should not, by unilateral measures, pollute the seas by dumping radioactive wastes, and Article 37 of the Euratom Treaty on the Commission's control over radioactive waste disposal plans by Member States constitute the principal legal basis for such activities at international level. The competent international organisations, IAEA and the OECD Nuclear Energy Agency (NEA), have both made detailed studies on the scientific, technical and legal aspects of sea disposal of radioactive wastes. Following consideration of the possibilities of waste dumping in the Atlantic and the related hazard assessment, at its Member State's request, NEA in 1967 undertook an initial experimental packaged waste disposal operation in the high seas. This operation's technical success encouraged Member States to undertake further operations in subsequent years under NEA international control. At present, in view of the entry into force of the London Convention on prevention of marine pollution by dumping of wastes, it seems desirable that the international character of such operations be preserved and all countries concerned be encouraged to adopt an international code of practice for sea disposal of radioactive wastes [fr

Reference biospheres for the long term safety assessment of radioactive waste disposal facilities

International Nuclear Information System (INIS)

Crossland, I.G.; Torres, C.

2002-01-01

Regulatory guidance on the safety assessment of radioactive waste disposals usually requires the consequences of any radionuclide releases to be considered in terms of their potential impact on human health. This requires consideration of the prevailing biosphere and the habits of the potentially exposed humans within it. However, it could take many thousands of years for migrating radionuclides to reach the surface environment. In these circumstances, an assessment model that was based on the present-day biosphere could be inappropriate while future biospheres would be unpredictable. These and other considerations suggest that a standardised, or reference biosphere, approach may be useful. Theme 1 of the IAEA BIOMASS project was established to develop the concept of reference biospheres into a practical system that can be applied to the assessment of the long term safety of geological disposal facilities for radioactive waste. The technical phase of the project lasted for four years until November 2000 and brought together disparate interests from many countries including waste disposal agencies, regulators and technical experts. Building on the experience from earlier BIOMOVS projects, a methodology was constructed for the logical and defensible construction of mathematical biosphere models that can be used in the total system performance assessment of radioactive waste disposal. The methodology was then further developed through the creation of a series of BIOMASS Example Reference Biospheres ('Examples'). These are stylised biosphere models that, in addition to illustrating the methodology, are intended to be useful assessment tools in their own right. (author)

Legal aspects of sub-seabed disposal of radioactive waste

International Nuclear Information System (INIS)

Reyners, P.

1981-10-01

In connection with methods for disposal of highly radioactive waste, that consisting of burying such waste in the sub-seabed arouses an increasingly marked interest among specialists. Apart from the technical difficulties still to be overcome and current safety assessments, this method gives rise to quite considerable legal and political problems. Their solution will undoubtedly have a bearing on its chances of being implemented. (NEA) [fr

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

Maxey Flats low-level waste disposal site closure activities

International Nuclear Information System (INIS)

Haight, C.P.; Mills, D.; Razor, J.E.

1987-01-01

The Maxey Flats Radioactive Waste Disposal Facility in Fleming County, Kentucky is in the process of being closed. The facility opened for commercial business in the spring of 1963 and received approximately 4.75 million cubic feet of radioactive waste by the time it was closed in December of 1977. During fourteen years of operation approximately 2.5 million curies of by-product material, 240,000 kilograms of source material, and 430 kilograms of special nuclear material were disposed. The Commonwealth purchased the lease hold estate and rights in May 1978 from the operating company. This action was taken to stabilize the facility and prepare it for closure consisting of passive care and monitoring. To prepare the site for closure, a number of remedial activities had to be performed. The remediation activities implemented have included erosion control, surface drainage modifications, installation of a temporary plastic surface cover, leachate removal, analysis, treatment and evaporation, US DOE funded evaporator concentrates solidification project and their on-site disposal in an improved disposal trench with enhanced cover for use in a humid environment situated in a fractured geology, performance evaluation of a grout injection demonstration, USGS subsurface geologic investigation, development of conceptual closure designs, and finally being added to the US EPA National Priority List for remediation and closure under Superfund. 13 references, 3 figures

Preliminary Transportation, Aging and Disposal Canister System Performance Specification

International Nuclear Information System (INIS)

C.A Kouts

2006-01-01

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. A list of system specified components and ancillary components are included in Section 1.2. The TAD canister, in conjunction with specialized overpacks will accomplish a number of functions in the management and disposal of spent nuclear fuel. Some of these functions will be accomplished at purchaser sites where commercial spent nuclear fuel (CSNF) is stored, and some will be performed within the Office of Civilian Radioactive Waste Management (OCRWM) transportation and disposal system. This document contains only those requirements unique to applications within Department of Energy's (DOE's) system. DOE recognizes that TAD canisters may have to perform similar functions at purchaser sites. Requirements to meet reactor functions, such as on-site dry storage, handling, and loading for transportation, are expected to be similar to commercially available canister-based systems. This document is intended to be referenced in the license application for the Monitored Geologic Repository (MGR). As such, the requirements cited herein are needed for TAD system use in OCRWM's disposal system. This document contains specifications for the TAD canister, transportation overpack and aging overpack. The remaining components and equipment that are unique to the OCRWM system or for similar purchaser applications will be supplied by others

Warranty obligations for the management and underground disposal of radioactive waste

International Nuclear Information System (INIS)

Jauho, P.; Silvennoinen, P.

1980-01-01

The need for financial assurances and institutional arrangements for waste management and disposal is discussed from the viewpoint of public interest. The basic principles stated in the paper include the requirement of accumulating funds for future contingencies during the active lifetime of the reactors and the fuel cycle facilities. A governmental role is seen as indispensable in assuming responsibility over at least the surveillance of underground repositories. The stage at which the operational responsibility is transferred from the plant operator to the government is determined in general by the status of the waste conditioning and disposal technology. A brief survey is presented of the current situation and technical issues.The need for special funds is discussed as well. For the part of waste management and disposal that will be taken over by the government an escrow fund should be established. Parallel to this public fund the plant operator would be obliged to reserve funds and provide guarantees within the company to cover liabilities for the remaining part of waste management and disposal obligations. A case study is presented in the paper covering the estimation of the escrow charges for spent fuel or high-level waste. (author)

Silicon-Polymer Encapsulation of High-Level Calcine Waste for Transportation or Disposal

International Nuclear Information System (INIS)

Loomis, G.G.; Miller, C.M.; Giansiracusa, J.A.; Kimmel, R.; Prewett, S.V.

2000-01-01

This report presents the results of an experimental study investigating the potential uses for silicon-polymer encapsulation of High Level Calcine Waste currently stored within the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The study investigated two different applications of silicon polymer encapsulation. One application uses silicon polymer to produce a waste form suitable for disposal at a High Level Radioactive Waste Disposal Facility directly, and the other application encapsulates the calcine material for transportation to an offsite melter for further processing. A simulated waste material from INTEC, called pilot scale calcine, which contained hazardous materials but no radioactive isotopes was used for the study, which was performed at the University of Akron under special arrangement with Orbit Technologies, the originators of the silicon polymer process called Polymer Encapsulation Technology (PET). This document first discusses the PET process, followed by a presentation of past studies involving PET applications to waste problems. Next, the results of an experimental study are presented on encapsulation of the INTEC calcine waste as it applies to transportation or disposal of calcine waste. Results relating to long-term disposal include: (1) a characterization of the pilot calcine waste; (2) Toxicity Characteristic Leaching Procedure (TCLP) testing of an optimum mixture of pilot calcine, polysiloxane and special additives; and, (3) Material Characterization Center testing MCC-1P evaluation of the optimum waste form. Results relating to transportation of the calcine material for a mixture of maximum waste loading include: compressive strength testing, 10-m drop test, melt testing, and a Department of Transportation (DOT) oxidizer test

The influence of disposal capacity on the course of site remediation

International Nuclear Information System (INIS)

Eng, J.

1999-01-01

The availability of, or more accurately the lack of, disposal capacity has altered the course of decontamination and decommissioning of radioactively contaminated sites. Political sensitivities in the 1970s caused a congressional restructuring of the disposal system in the United States. At the same time, the 1970s saw a movement towards reexamining many previously decontaminated facilities with a new emphasis on environmental protection. A reexamination of accessibility to disposal capacity began in the 1980s because the three states with disposal facilities wanted to restrict use of their facilities and create new capacity in other states. The passage of the federal Low-Level Radioactive Waste Policy Act and Amendments Act permitted states to form compacts to restrict use of disposal facilities in their region. The Amendments Act also permitted the collection of surcharges that ultimately increased the cost of disposal by 300% within a decade. Radioactive facilities that were reevaluated include radium facilities of the first decades of the Twentieth Century, government and private facilities that took part in atomic weapon development during the World War II era, and older facilities licensed under the Atomic Energy Act in the latter half of the century. The reevaluations resulted in modern day conclusions that further remedial actions may be needed. The solution appeared straightforward: removal of the radiological contamination that is in excess of current day environmental standards. The large volumes of slightly contaminated debris and the limited, costly disposal capacity have created a need for alternatives to excavation and removal. Some of the techniques have created opportunities such as specialized disposal sites (e.g., Envirocare), reuse of contaminated metals, more aggressive decontamination processes, and recycling (e.g., mill reprocessing). (author)

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)

Geographic factors related to site suitability of low-level waste disposal

International Nuclear Information System (INIS)

Zittel, H.E.

1981-01-01

A number of factors related to the site suitability of low-level waste disposal sites are discussed. The factors are a combination of those which might be considered environmental and those dealing with site criteria. Among the factors covered are: possible population criteria, alternative site selection, transportation criteria and community involvement considerations. All these factors are discussed in a manner based on the premise that the technology exists to carry out low-level waste disposal in a manner such that public health and safety can be insured. The conclusion of the discussion is that problems encountered in siting low-level waste facilities will be largely societal and political in nature

Site identification: environmental and radiological considerations

International Nuclear Information System (INIS)

Waite, D.A.

1980-01-01

Radiological and environmental considerations are recognized as being of utmost importance in planning, siting, licensing, operating, and decommissioning a high-level nuclear waste repository. In such a complex undertaking, it is important to identify the major concerns anticipated to arise in all of these phases in order to address them as early as possible in the program. Three representative activities/studies are summarized which will identify some of the important radiological and environmental considerations which must be addressed through this prolonged sequence of events and will indicate how these considerations are being addressed. It should be emphasized that these are only three of many which could have been chosen. The three key activities/studies are: (1) the NWTS Program criteria for identifying repository sites, (2) the generic guide for preparing environmental evaluations for deep drilling and (3) a preliminary environmental assessment for disposal of mined rock during excavation of a repository

7 CFR 932.155 - Special purpose shipments.

Science.gov (United States)

2010-01-01

... and Regulations § 932.155 Special purpose shipments. (a) The disposition of packaged olives covered by... Service, such packaged olives may be disposed of for use in the production of olive oil or dumped. (2... furnish the committee, upon demand, such evidence of disposition of the packaged olives covered by an...

Corrosion problems related to the containment of high-level nuclear waste for disposal

Energy Technology Data Exchange (ETDEWEB)

Rothwell, G P

1981-10-01

The subject is examined under the headings: introduction (nature of problem; system of barriers which will initially contain the wasteform and subsequently limit the rate of transport of products from the wasteform to the external environment); environmental data (disposal in land-based repositories; disposal on or in the deep seabed); design philosophies and materials data (design; criteria for materials selection (kinetics of corrosion)); specific materials considerations (environmental parameters -temperature, pressure, heat transfer and radiation effects; single metals and alloys - steels, nickel based alloys, copper, lead, titanium, aluminium oxide); alternative approaches; an overview - information needs; summary.

SITEX, the European Network of Technical Expertise Organisation for Geological Disposal

International Nuclear Information System (INIS)

Pellegrini, D.; Rocher, M.; Bernier, F.; Detilleux, V.; Hériard Dubreuil, G.; Narkuniene, A.; Miksova, J.

2016-01-01

Objective: To identify and prioritize the needs for competence and skills development of the Expertise Function, at the international level. Commitments: − The SRA is developed by applying a transparent methodology; − The SRA addresses the needs associated with the different states of advancement of geological disposal (GD) programmes; The concerns of civil society are taken into consideration. Scope of the SRA: ‒ All the topics relevant to the Expertise Function to assess whether geological disposal facilities are developed and will be constructed, operated and closed in a safe manner. ‒ It encompasses all topics relevant to any waste type and spent fuel for which geological disposal is envisaged as a solution for its long-term management. ‒ The following types of activity are considered: • R&D activities; • exchanging on practices and developing common positions; • developing states of the art; • knowledge transfer (e.g. training or tutoring)

Consideration of disposal alternatives for tritium-contaminated wastewater streams at Hanford

International Nuclear Information System (INIS)

Waters, E.D.

1988-03-01

Small quantities of tritium are produced as an undesirable by-product of the operation of light-water reactors. At the US Department of Energy Hanford Site in Washington State, some tritium has been discharged to the environment in low-level liquid and gaseous wastes from the N Reactor plant, but more than 97% of the tritium stays typically within the irradiated fuel as it is delivered for reprocessing. During fuel reprocessing, the tritium is distributed in the process streams, and most of the tritium is presently released to the soil column with excess process condensates from the Plutonium-Uranium Extraction (PUREX) Plant. On an annual basis, approximately 1 g of tritium is discharged in more than 1 x 10 6 L of process condensate water. Principal tritium release points and quantities are presented in section 4.0. The present study is intended to identify and evaluate alternate methods of tritium control and disposal that might merit additional study or development for potential application to Hanford Site effluents. 30 refs., 15 figs., 5 tabs

Institutional storage and disposal of radioactive materials

International Nuclear Information System (INIS)

St Germain, J.

1986-01-01

Storage and disposal of radioactive materials from nuclear medicine operations must be considered in the overall program design. The storage of materials from daily operation, materials in transit, and long-term storage represent sources of exposure. The design of storage facilities must include consideration of available space, choice of material, occupancy of surrounding areas, and amount of radioactivity anticipated. Neglect of any of these factors will lead to exposure problems. The ultimate product of any manipulation of radioactive material will be some form of radioactive waste. This waste may be discharged into the environment or placed within a storage area for packaging and transfer to a broker for ultimate disposal. Personnel must be keenly aware of packaging regulations of the burial site as well as applicable federal and local codes. Fire codes should be reviewed if there is to be storage of flammable materials in any area. Radiation protection personnel should be aware of community attitudes when considering the design of the waste program

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.

Disposal of olive oil mill wastes in evaporation ponds: effects on soil properties.

Science.gov (United States)

Kavvadias, V; Doula, M K; Komnitsas, K; Liakopoulou, N

2010-10-15

The most common practice followed in the Med countries for the management of olive oil mill wastes (OMW) involves disposal in evaporation ponds or direct disposal on soil. So far there is lack of reliable information regarding the long-term effects of OMW application on soils. This study assesses the effects of OMW disposal in evaporation ponds on underlying soil properties in the wider disposal site as well as the impacts of untreated OMW application on agricultural soils. In case of active disposal sites, the carbonate content in most soils was decreased, whereas soil EC, as well as Cl(-), SO(4)(2-), PO(4)(3-), NH(4)(+) and particularly K(+) concentrations were substantially increased. Soil pH was only marginally affected. Phenol, total N, available P and PO(4)(3-) concentrations were considerably higher in the upper soil layers in areas adjacent to the ponds. Available B as well as DTPA extractable Cu, Mn, Zn and Fe increased substantially. Most surface soil parameters exhibited increased values at the inactive site 6 years after mill closure and cease of OMW disposal activities but differences were diminished in deeper layers. It is therefore concluded that long-term uncontrolled disposal of raw OMW on soils may affect soil properties and subsequently enhance the risk for groundwater contamination. 2010 Elsevier B.V. All rights reserved.

Report to the Radioactive Waste Management Committee on the first international workshop on seabed disposal of high-level wastes

International Nuclear Information System (INIS)

Anderson, D.R.; Hollister, C.D.; Talbert, D.M.

1976-01-01

The basic conclusion of the workshop is that, while a very considerable amount of work must be done to assure safety and feasibility, no technical reasons are apparent at this moment that would preclude disposal of radioactive wastes underneath the seafloor. Subsidiary conclusions reached by subgroups dealing with undersea geology, biology, the water column, and disposal canister research are given. General conclusions reached by the workshop are detailed, together with proposals for an international program furthering an undersea disposal scheme

Radioactive waste disposal

International Nuclear Information System (INIS)

Petit, J.C.

1998-04-01

A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their 'hydridation'. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a 'rape' and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects

A brief analysis and description of transuranic wastes in the subsurface disposal area of the radioactive waste management complex at INEL

International Nuclear Information System (INIS)

Arrenholz, D.A.; Knight, J.L.

1991-02-01

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area during the period 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and special-case wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and makes recommendations for future efforts at waste characterization. 20 refs., 3 figs., 17 tabs

The treatment and disposal of liquid waste in the nuclear power industry

International Nuclear Information System (INIS)

Lewis, J.B.

1978-01-01

Paper presented by the head of the Industrial Chemistry Group at AERE Harwell at a symposium held by the University of Newcastle upon Tyne (UK) in association with the Institute of Water Pollution Control and the Institution of Chemical Engineers in September 1977. Main headings are as follows: general introduction; units of measurement of radioactivity; environmental considerations (disposal authorisations, natural background, critical path approach, discharges to the sea, discharges to rivers); types of liquid waste (general, high level wastes, wastes from chemical processing stages, wastes from nuclear power stations, miscellaneous wastes); treatment techniques (general, evaporation, chemical precipitation, ion exchange, reverse osmosis, electrodialysis); disposal of radioactive concentrates (high level wastes, sludges, exhausted ion exchangers, etc.). It is concluded that the main task remaining is to find the best means of ultimate disposal of high level wastes. (U.K.)

Reversibility and retrievability in geologic disposal of radioactive waste

International Nuclear Information System (INIS)

2001-01-01

Reversibility of decisions is an important consideration in the step-wise decision-making process that is foreseen for engineered geologic disposal of radioactive waste. The implications of favouring retrievability of the waste within disposal strategies and the methods to implement it are also being considered by NEA Member countries. This report reviews the concepts of reversibility and retrievability as they may apply to the planning and development of engineered geologic repositories. The concepts span technical, policy and ethical issues, and it is important that a broad understanding is developed of their value and implications. Furthermore, improved comprehension and communication of these issues will clarify the value of flexible, step-wise decision making in repository development programmes and may help to generate a climate conducive to the further progress of such programmes. (author)

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

The disposal of redundant teletherapy units from NHS hospitals

International Nuclear Information System (INIS)

Gaffka, A.P.; Ord, M.A.

1994-01-01

The removal/disposal of redundant teletherapy units from NHS hospitals is described, detailing the operational procedures and the transport package background. The Harwell section of the Transport Technology Department has been carrying out these operations since 1991, where initially the service was just offered to the NHS; however, today their specialist transport service has significantly widened and is now offered to other business sectors. Due to the level of radioactivity found in each teletherapy unit, it was necessary to design a special transport packaging to meet the requirements for shipment of these units. Approval was sought from the Department of Transport to adapt a standard Type B package as no other packaging could be found to comply with the necessary requirements. All work undertaken on the removal and disposal of these units complied with an approved scheme of work and was carried out in accordance with a Quality Assurance workplan. However, to keep abreast of modern standards in a manner which is cost effective to customers and acceptable to the general public, the full development of a new Type B packaging is taking place, which is specifically designed to undertake these removal/disposal duties. (author)

Greater-Than-Class C Low Level Radioactive Waste Characteristics and Disposal Aspects

International Nuclear Information System (INIS)

Arlt, Hans D.; Brimfield, Terrence; Grossman, Chris

2016-01-01

Conclusions • Due to the way LLRW is defined in the US, there is a category of LLRW (i.e., GTCC waste) that was categorized in the 1980’s and is similar to ILW and not generally acceptable for near-surface disposal. • Three decades later, it cannot be excluded that future NRC analyses may find some GTCC waste type suitable for near-surface disposal, and a proposed rule may be developed for licensing the disposal of such waste. • Current regulations only allow individual proposals for GTCC LLRW disposal to be evaluated on a case-by-case basis to determine the acceptability of land disposal other than in a geologic repository • Based on current regulations, the variability and diversity of FEPs associated with such safety cases is theoretically large: - The range of activity concentrations, half-lives, and volumes of GTCC waste types is large; - The range of physical forms is large: metal pieces to soils and sludges; - The range of potential disposal methods is large: trench, vault, landfill, shaft, borehole; - The range of potential disposal environments is large: arid vs. humid, unsaturated vs. saturated, sediment vs. rock, nearsurface to intermediate; - The stability and past natural history of a specific disposal site must also be adequately known. • Examples of potential site-specific cases designed to demonstrate the acceptability of GTCC LLRW land disposal other than deep geologic: - Proposals for disposal could entail concepts that have been relatively well assessed by NRC staff in the past; e.g., trench disposal of a moderate volume of GTCC Other Waste in an arid, unsaturated, near-surface environment; - Proposals for disposal could also entail concepts that have been less frequently assessed; e.g., borehole disposal of higher activity sealed sources in a humid, saturated, intermediate depth environment. • However, if one potential site and design was under consideration, the variability and diversity of FEPs associated with that site

Evaluation of Island and Nearshore Confined Disposal Facility Alternatives, Pascagoula River Harbor Dredged Material Management Plan

National Research Council Canada - National Science Library

Bunch, Barry

2003-01-01

...) for the Federal navigation project at Pascagoula, MS. The studies focused on evaluating an option under consideration for the placement of dredged material in an island confined disposal facility (CDF...

Finite-element model evaluation of barrier configurations to reduce infiltration into waste-disposal structures: preliminary results and design considerations

International Nuclear Information System (INIS)

Lu, A.H.; Phillips, S.J.; Adams, M.R.

1982-09-01

Barriers to reduce infiltration into waste burial disposal structures (trenches, pits, etc.) may be required to provide adequate waste confinement. The preliminary engineering design of these barriers should consider interrelated barrier performance factors. This paper summarizes preliminary computer simulation activities to further engineering barrier design efforts. Several barrier configurations were conceived and evaluated. Models were simulated for each barrier configuration using a finite element computer code. Results of this preliminary evaluation indicate that barrier configurations, depending on their morphology and materials, may significantly influence infiltration, flux, drainage, and storage of water through and within waste disposal structures. 9 figures

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

Summary of key directives governing permanent disposal in a geologic repository

International Nuclear Information System (INIS)

Sands, S.C. III.

1993-11-01

This document was developed in support of the Idaho National Engineering Laboratory (INEL) Spent Fuel and Waste Management Technology Development Program (SF ampersand WMTDP). It is largely comprised of flow diagrams summarizing the key regulatory requirements which govern permanent disposal in a geologic repository. The key purposes are (1) to provide an easy and effective tool for referencing or cross referencing federal directives (i.e., regulations and orders), (2) to provide a method for examining the requirements in one directive category against the requirements in another, and (3) to list actions that must be taken to ensure directive compliance. The document is categorically broken down into a Transportation section and a Mined Geologic Disposal System (MGDS) section to ensure that the interrelationship of the entire disposal system is considered. The Transportation section describes the transportation packaging requirements, testing methods, and safety requirements imposed on fissile material shipments. The MGDS section encompasses technical aspects involved in siting, licensing, waste interaction with the container, container design features, physical characteristics of the surrounding environment, facility design features, barrier systems, safety features, criticality considerations, migration restrictions, implementation guidelines, and so forth. For purposes of illustration, the worst case scenario is outlined. It is important that the approaches and considerations contained in this document be integrated into the efforts of the SF ampersand WMTDP so that every applicable aspect of the regulatory requirements can be evaluated to avoid investing large sums of money into projects that do not take into account all of the aspects of permanent waste disposal. Not until an overall picture and clear understanding of these regulations is established can a basis be developed to govern the direction of future activities of the SF ampersand WMTDP

Safety assessment of HLW geological disposal system

International Nuclear Information System (INIS)

Naito, Morimasa

2006-01-01

In accordance with the Japanese nuclear program, the liquid waste with a high level of radioactivity arising from reprocessing is solidified in a stable glass matrix (vitrification) in stainless steel fabrication containers. The vitrified waste is referred to as high-level radioactive waste (HLW), and is characterized by very high initial radioactivity which, even though it decreases with time, presents a potential long-term risk. It is therefore necessary to thoroughly manage HLW from human and his environment. After vitrification, HLW is stored for a period of 30 to 50 years to allow cooling, and finally disposed of in a stable geological environment at depths greater than 300 m below surface. The deep underground environment, in general, is considered to be stable over geological timescales compared with surface environment. By selecting an appropriate disposal site, therefore, it is considered to be feasible to isolate the waste in the repository from man and his environment until such time as radioactivity levels have decayed to insignificance. The concept of geological disposal in Japan is similar to that in other countries, being based on a multibarrier system which combines the natural geological environment with engineered barriers. It should be noted that geological disposal concept is based on a passive safety system that does not require any institutional control for assuring long term environmental safety. To demonstrate feasibility of safe HLW repository concept in Japan, following technical steps are essential. Selection of a geological environment which is sufficiently stable for disposal (site selection). Design and installation of the engineered barrier system in a stable geological environment (engineering measures). Confirmation of the safety of the constructed geological disposal system (safety assessment). For site selection, particular consideration is given to the long-term stability of the geological environment taking into account the fact

Organisation of the disposal of radioactive sources from Scottish hospitals

International Nuclear Information System (INIS)

Corrigall, R S; Martin, C J; Watson, I

2004-01-01

An amnesty for disposal of sealed radioactive sources from Scottish hospitals has been funded by the Scottish Executive to address problems arising from accumulation of sources. The contract was awarded to a company involved in radioactive source recycling. Coordination of uplifts from several hospitals allowed considerable financial savings to be made, so source amnesties could offer monetary advantages to Health and Education Departments elsewhere in the UK, as well as alleviating the problem from security and storage of sources that are no longer required. The sources originated in 14 hospitals, but were uplifted from five pick-up points. There were a total of 246 sources with 167 of these being caesium-137. The total activity was 16.2 TBq with one large 16.1 TBq blood irradiator source and the activities of all the other sources adding up to 167 GBq. This paper describes organisation of the collection. Options for achieving compliance with the Radioactive Substances Act 1993 are discussed, although in the event, special authorisations were obtained for each hospital. Arrangements for transport of the sources and source security were drawn up including emergency procedures for dealing with foreseeable incidents. The police provided secure overnight storage for the loaded truck and assistance in directing and monitoring progress of the load

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

Radioactive waste disposal in geological formations

International Nuclear Information System (INIS)

Gera, F.

1977-01-01

The nuclear energy controversy, now raging in several countries, is based on two main issues: the safety of nuclear plants and the possibility to dispose safely of the long-lived radioactive wastes. Consideration of the evolution of the hazard potential of waste in function of decay time leads to a somewhat conservative reference containment time in the order of one hundred thousand years. Several concepts have been proposed for the disposal of long-lived wastes. At the present time, emplacement into suitable geological formations under land areas can be considered the most promising disposal option. It is practically impossible to define detailed criteria to be followed in selecting suitable sites for disposal of long-lived wastes. Basically there is a single criterion, namely; that the geological environment must be able to contain the wastes for at least a hundred thousand years. However, due to the extreme variability of geological settings, it is conceivable that this basic capability could be provided by a great variety of different conditions. The predominant natural mechanism by which waste radionuclides could be moved from a sealed repository in a deep geological formation into the biosphere is leaching and transfer by ground water. Hence the greatest challenge is to give a satisfactory demonstration that isolation from ground water will persist over the required containment time. Since geological predictions are necessarily affected by fairly high levels of uncertainty, the only practical approach is not a straight-forward forecast of future geological events, but a careful assessment of the upper limits of geologic changes that could take place in the repository area over the next hundred thousand years. If waste containment were to survive these extreme geological changes the disposal site could be considered acceptable. If some release of activity were to take place in consequence of the hypothetical events the disposal solution might still be

Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0

International Nuclear Information System (INIS)

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-01

Following President Clinton's Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations

Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0

Energy Technology Data Exchange (ETDEWEB)

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15

Following President Clinton`s Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations.

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 APPLICATION OF THE SPECIALTY PRINCIPLE, CONCERNING THE SPECIAL SEIZURE IN ROMANIAN CRIMINAL LAW

Directory of Open Access Journals (Sweden)

MONICA POCORA

2011-04-01

Full Text Available This paper aims to be a comparative analysis of the special seizure as a safety measure, as it is regulated in Romanian special criminal legislation, and also a way to highlight certain discrepancies between the general and special criminal legislation. Special seizure, as a safety measure, may be disposed under Criminal Code regulations, as a general norm, but also under some stipulations included in special Criminal laws. Moreover, when there are such special stipulations, they have under the rules of specialty principle, priority in implementing to the general norm. In our opinion, in these cases, special seizure is also disposed under the Criminal Code provisions, as general norm, because the general terms nondescript by others field of incidence, are the ones who set by the Criminal law. In fact, in such cases, the special seizure is ordered under both Criminal provisions. In analysis of the paper, is made reference to the applicability of special seizure measure inmatter of corruption offences, in customs, money laundering, illicit trafficking of drugs and fisheries and fish farming, and as a result of their presentation, we concluded that although is in question the specialty principle, mainly would find application the general norm in comparison with special norm. Moreover, corroborating the actually general norm with the provisions of the New Criminal Code, we believe the special seizure, should operate exclusively under the general law, or the provisions of the special norm, should be modified.

MethodS of radioactive waste processing and disposal in the United Kingdom

International Nuclear Information System (INIS)

Tolstykh, V.D.

1983-01-01

The results of investigations into radioactive waste processing and disposal in the United Kingdom are discussed. Methods for solidification of metal and graphite radioactive wastes and radioactive slime of the Magnox reactors are described. Specifications of different installations used for radioactive waste disposal are given. Climatic and geological conditions in the United Kingdom are such that any deep storages of wastes will be lower than the underground water level. That is why dissolution and transport by underground waters will inevitably result in radionuclide mobility. In this connection an extended program of investigations into the main three aspects of disposal problem namely radionucleide release in storages, underground water transport and radionuclide migration is realized. The program is divided in two parts. The first part deals with retrival of hydrological and geochemical data on geological formations, development of specialized methods of investigations which are necessary for identification of places for waste final disposal. The second part represents theoretical and laboratory investigations into provesses of radionuclide transport in the system of ''sttorage-geological formation''. It is concluded that vitrification on the base of borosilicate glass is the most advanced method of radioactive waste solidification

Numerical modeling of cracking pattern's influence on the dynamic response of thickened tailings disposals: a periodic approach

Science.gov (United States)

Ferrer, Gabriel; Sáez, Esteban; Ledezma, Christian

2018-01-01

Copper production is an essential component of the Chilean economy. During the extraction process of copper, large quantities of waste materials (tailings) are produced, which are typically stored in large tailing ponds. Thickened Tailings Disposal (TTD) is an alternative to conventional tailings ponds. In TTD, a considerable amount of water is extracted from the tailings before their deposition. Once a thickened tailings layer is deposited, it loses water and it shrinks, forming a relatively regular structure of tailings blocks with vertical cracks in between, which are then filled up with "fresh" tailings once the new upper layer is deposited. The dynamic response of a representative column of this complex structure made out of tailings blocks with softer material in between was analyzed using a periodic half-space finite element model. The tailings' behavior was modeled using an elasto-plastic multi-yielding constitutive model, and Chilean earthquake records were used for the seismic analyses. Special attention was given to the liquefaction potential evaluation of TTD.

Impact of urban waste water treatment on sludge utilization and disposal with special emphasis on thermal treatment

International Nuclear Information System (INIS)

Gammeltoft, P.

1993-01-01

The acceptance of the European Communities Directive 9/271/CEE concerning urban waste water treatment by all the EC Member States will result in a sewage sludge production increase of 2 to 3 times the actual amounts (for the year 2000 the forecast is about 30 million tonnes per year). All the traditional sewage sludge treatment methods (agricultural, disposal, compost, thermal treatment) entail costs which are always increasing because of the stricter requirements; in addition EC policy is oriented towards the reduction of the quantity of sludge production. In some situations, drying and subseque incineration may thus be the only practicable method of disposal, particularly, in very large urban agglomerations

Corrosion problems related to the containment of high-level nuclear waste for disposal

International Nuclear Information System (INIS)

Rothwell, G.P.

1981-01-01

The subject is examined under the headings: introduction (nature of problem; system of barriers which will initially contain the wasteform and subsequently limit the rate of transport of products from the wasteform to the external environment); environmental data (disposal in land-based repositories; disposal on or in the deep seabed); design philosophies and materials data (design; criteria for materials selection (kinetics of corrosion)); specific materials considerations (environmental parameters -temperature, pressure, heat transfer and radiation effects; single metals and alloys - steels, nickel based alloys, copper, lead, titanium, aluminium oxide); alternative approaches; an overview - information needs; summary. (U.K.)

Should the U.S. proceed to consider licensing deep geological disposal of high-level nuclear waste

International Nuclear Information System (INIS)

Curtiss, J.R.

1993-01-01

The United States, as well as other countries facing the question of how to handle high-level nuclear waste, has decided that the most appropriate means of disposal is in a deep geologic repository. In recent years, the Radioactive Waste Management Committee of the Nuclear Energy Agency has developed several position papers on the technical achievability of deep geologic disposal, thus demonstrating the serious consideration of deep geologic disposal in the international community. The Committee has not, as yet, formally endorsed disposal in a deep geologic repository as the preferred method of handling high-level nuclear waste. The United States, on the other hand, has studied the various methods of disposing of high-level nuclear waste, and has determined that deep geologic disposal is the method that should be developed. The purpose of this paper is to present a review of the United States' decision on selecting deep geologic disposal as the preferred method of addressing the high-level waste problem. It presents a short history of the steps taken by the U.S. in determining what method to use, discusses the NRC's waste Confidence Decision, and provides information on other issues in the U.S. program such as reconsideration of the final disposal standard and the growing inventory of spent fuel in storage

Ethical Considerations Regarding the Biological Contamination of Climatically Recurrent Special Regions.

Science.gov (United States)

Clifford, S. M.

2014-04-01

With the dawn of planetary exploration, the international science community expressed concerns regarding the potential contamination of habitable planetary environments by the introduction of terrestrial organisms on robotic spacecraft. The initial concern was that such contamination would confound our efforts to find unambiguous evidence of life elsewhere in the Solar System, although, more recently, this concern has been expanded to include ethical considerations regarding the need to protect alien biospheres from potentially harmful and irreversible contamination. The international agreements which address this concern include the UN Space Treaty of 1967 and the Planetary Protection Policy of the International Council for Science's Committee on Space Research (COSPAR). In the context of Mars exploration, COSPAR calls a potentially habitable environment a 'Special Region', which it defines as: "A region within which terrestrial organisms are likely to propagate, or a region which is interpreted to have a high potential for the existence of extant Martian life forms." Specifically included in this definition are regions where liquid water is present or likely to occur and the Martian polar caps. Over the years, scientists have debated the level of cleanliness required for robotic spacecraft to investigate such environments with the goal of defining international standards that are strict enough to ensure the integrity of life-detection efforts during the period of 'biological exploration', which has been somewhat arbitrarily defined as 50 years from the arrival date of any given mission. More recently, NASA and ESA have adopted a definition of Special Regions as any Martian environment where liquid water is likely to exist within the next 500 years. While this appears to be a more conservative interpretation of the original COSPAR definition, it specifically excludes some environments where there is a high probability of liquid water on timescales greater than 500

Subseabed disposal program annual report, January-December 1978. Volume II. Principal investigator progress reports

International Nuclear Information System (INIS)

1979-10-01

The topics covered in this report include: geologic siting considerations for the disposal of radioactive wastes into submarine geologic formations; geologic assessment of the MPG-1 regions Central North Pacific; site mapping; geotechnical aspects of subsurface seabed disposal; heat transfer, thermal and fluid physics in the deep ocean sediments; mechanical response predictive capability; sediment-seawater interaction at 300 0 C, 500 bars; stability of actinides in chloride media; cannister corrosion studies; nuclide sorption and migration; development of apparatus and measurement of thermal conductivity of seabed illite and smectite at temperatures to 500 0 C at simulated depths to 15,000 ft (9000 psi); in-situ heat transfer experiments; preliminary seabed disposal transport modeling studies; radionuclide migration studies; radionuclide distributions in deep ocean cores; benthic biological studies; deep sea microbial studies; activity rates of abyssal communities; Deep-towed RUM III (Sandia Seabed working platform): a third-generation remote underwater manipulator; long coring facility program; transportation; legal, political, and institutional implications of the Seabed Program for radioactive waste disposal

On barrier performance of high compaction bentonite in facilities of disposing high level radioactive wastes in formation

International Nuclear Information System (INIS)

Ikeda, Hidefumi; Komada, Hiroya

1989-01-01

As for the method of disposing high level radioactive wastes generated in the reprocessing of spent fuel, at present formation disposal is regarded as most promising. The most important point in this formation disposal is to prevent the leak of radioactive nuclides within the disposal facilities into bedrocks and their move to the zone of human life. As the method of formation disposal, the canisters containing high level radioactive wastes are placed in the horizontal or vertical holes for disposal dug from horizontal tunnels which are several hundreds m underground, and the tunnels and disposal holes are filled again. For this filling material, the barrier performance to prevent and retard the leak of radioactive nuclides out of the disposal facilities is expected, and the characteristics of low water permeability, the adsorption of nuclides and long term stability are required. However, due to the decay heat of wastes just after the disposal, high temperature and drying condition arises, and this must be taken in consideration. The characteristics required for filling materials and the selection of the materials, the features and classification of bentonite, the properties of high compaction bentonite, and the move of water, heat and nuclides in high compaction bentonite are reported.(Kako, I.)

Scientific Considerations for the Assessment and Management of Mine Tailings Disposal in the Deep Sea

Directory of Open Access Journals (Sweden)

Lindsay L. Vare

2018-02-01

Full Text Available Deep-sea tailings disposal (DSTD and its shallow water counterpart, submarine tailings disposal (STD, are practiced in many areas of the world, whereby mining industries discharge processed mud- and rock-waste slurries (tailings directly into the marine environment. Pipeline discharges and other land-based sources of marine pollution fall beyond the regulatory scope of the London Convention and the London Protocols (LC/LP. However, guidelines have been developed in Papua New Guinea (PNG to improve tailings waste management frameworks in which mining companies can operate. DSTD can impact ocean ecosystems in addition to other sources of stress, such as from fishing, pollution, energy extraction, tourism, eutrophication, climate change and, potentially in the future, from deep-seabed mining. Environmental management of DSTD may be most effective when placed in a broader context, drawing expertise, data and lessons from multiple sectors (academia, government, society, industry, and regulators and engaging with international deep-ocean observing programs, databases and stewardship consortia. Here, the challenges associated with DSTD are identified, along with possible solutions, based on the results of a number of robust scientific studies. Also highlighted are the key issues, trends of improved practice and techniques that could be used if considering DSTD (such as increased precaution if considering submarine canyon locations, likely cumulative impacts, and research needed to address current knowledge gaps.

Techno-economical Analysis of High Level Waste Storage and Disposal Options

International Nuclear Information System (INIS)

Bace, M.; Trontl, K.; Vrankic, K.

2002-01-01

Global warming and instability of gas and oil prices are redefining the role of nuclear energy in electrical energy production. A production of high-level radioactive waste (HLW), during the nuclear power plant operation and a danger of high level waste mitigation to the environment are considered by the public as a main obstacle of accepting the nuclear option. As economical and technical aspects of the back end of fuel cycle will affect the nuclear energy acceptance the techno-economical analysis of different methods for high level waste storage and disposal has to be performed. The aim of this paper is to present technical and economical characteristics of different HLW storage and disposal technologies. The final choice of a particular HLW management method is closely connected to the selection of a fuel cycle type: open or closed. Wet and dry temporary storage has been analyzed including different types of spent fuel pool capacity increase methods, different pool location (at reactor site and away from reactor site) as well as casks and vault system of dry storage. Since deep geological deposition is the only disposal method with a realistic potential, we focused our attention on that disposal technology. Special attention has been given to the new idea of international and regional disposal location. The analysis showed that a coexistence of different storage methods and deep geological deposition is expected in the future, regardless of the fuel cycle type. (author)

Ocean disposal of radioactive waste: Status report

International Nuclear Information System (INIS)

Calmet, D.P.

1989-01-01

For hundreds of years, the seas have been used as a place to dispose of wastes resulting from human activities and although no high level radioactive waste (HLW) has been disposed of into the sea, variable amounts of packaged low level radioactive waste (LLW) have been dumped at more than 50 sites in the northern part of the Atlantic and Pacific oceans. So far, samples of sea water, sediments and deep sea organisms collected on the various sites have not shown any excess in the levels of radionuclides above those due to nuclear weapons fallout except on certain occasions where caesium and plutonium were detected at higher levels in samples taken close to packages at the dumping site. Since 1957, the date of its first meeting to design methodologies to assess the safety of ''radioactive waste disposal into the sea'', the IAEA has provided guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. Since the Convention for the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (referred to as the London Dumping Convention) came into force in 1975, the dumping of waste has been regulated on a global scale. The London Dumping Convention entrusted IAEA with specific responsibilities for the definition of high level radioactive wastes unsuitable for dumping at sea, and for making recommendations to national authorities for issuing special permits for ocean dumping of low level radioactive wastes. This paper presents a status report of immersion operations of low-level radioactive waste and the current studies the IAEA is undertaking on behalf of the LDC

Ethical aspects in connection with the disposal of radioactive wastes

International Nuclear Information System (INIS)

Boetsch, W.

2003-01-01

The progress of modern natural and technological science and their far-reaching consequences affecting the distant future require increasingly practice-oriented ethical concepts. In the discussions about responseable acting, the question of the ethical tenability of nuclear energy nowadays takes a special position. Above all the problem of the disposal of radioactive wastes - the effects of which on the distant future have to be prognosticated - is controversially discussed in society. The Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) commissioned Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS) in the context of the project ''Disposal of radioactive wastes in the context of ethical objectives'' to summarise the current national and international status of ethical aspects in connection with the disposal of radioactive wastes. One aim of this report is to derive criteria to form the basis of a comprehensive discussion of the ethical aspects of the disposal of radioactive wastes. These criteria are to describe, as far as possible, all content-related aspects that result from radioactive waste disposal. The issues in this report resulting from the opinions, comments and publications presented are to serve as a basis for an experts' meeting at which the important ethical criteria concerning the responsible management of radioactive waste disposal are to be discussed at an interdisciplinary level with all those involved. The results of this report are based on an investigation which gathered the available national and international statements, principles, and criteria relating to the ethical aspects of the disposal of radioactive wastes and to sustainable development in the context of the technological impact assessment up to beginning of 2000. In the meantime, the debate in Germany has become somewhat more pragmatic, i. a. due to the work of the research group ''Arbeitskreis Auswahlverfahren Endlagerstandorte (AkEnd)'' and

Disposal of spent fuel from German nuclear power plants - 16028

International Nuclear Information System (INIS)

Graf, Reinhold; Brammer, Klaus-Juergen; Filbert, Wolfgang; Bollingerfehr, Wilhelm

2009-01-01

The 'direct disposal of spent fuel' as a part of the current German reference concept was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this part of the reference concept, the so called POLLUX R concept, i.e. interim storage buildings for casks containing spent fuel, a pilot conditioning facility, and a special cask 'POLLUX' for final disposal have been built. With view to a geological salt formation all handling procedures for the direct disposal of spent fuel were tested aboveground in full-scale test facilities. To optimise the reference concept, all operational steps have been reviewed for possible improvements. The two additional concepts for the direct disposal of SF are the BSK 3 concept and the DIREGT concept. Both concepts rely on borehole emplacement technology, vertical boreholes for the BSK 3 concept und horizontal boreholes for the DIREGT concept. Supported by the EU and the German Federal Ministry of Economics and Technology (BMWi), DBE TECHNOLOGY built an aboveground full-scale test facility to simulate all relevant handling procedures for the BSK 3 disposal concept. GNS (Company for Nuclear Service), representing the German utilities, provided the main components and its know-how concerning cask design and manufacturing. The test program was concluded recently after more than 1.000 emplacement operations had been performed successfully. The BSK 3 emplacement system in total comprises an emplacement device, a borehole lock, a transport cart, a transfer cask which will shuttle between the aboveground conditioning facility and the underground repository, and the BSK 3 canister itself, designed to contain the fuel rods of three PWR-fuel assemblies with a total of about 1.6 tHM. The BSK 3 concept simplifies the operation of the repository because the handling procedures and techniques can also be applied for the disposal of reprocessing residues. In addition

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)

Geotechnical aspects of deep ocean radioactive waste disposal

International Nuclear Information System (INIS)

Freeman, T.J.

1990-01-01

The methods that might be used to bury radioactive waste in the deep ocean, and their likely effect on the sediment barrier, have been the subject of an international research program performed during the last ten years. This paper reviews the geotechnical aspects of deep ocean disposal and discusses how far the research performed has gone towards providing the information needed to assess this form of disposal. Considerable progress has been made during the course of the international program towards understanding the processes involved in the emplacement of heat generating waste (HGW) into the deep ocean bed and the subsequent interactions between the waste and the sediments. These processes do not appear to have a deleterious effect on the barrier properties of the sediments, and it is concluded that it is likely that HGW could be emplaced in the deep ocean in such a way that the seabed would provide an effective containment for the radionuclides

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.

Disposal options for polluted plants grown on heavy metal contaminated brownfield lands - A review.

Science.gov (United States)

Kovacs, Helga; Szemmelveisz, Katalin

2017-01-01

Reducing or preventing damage caused by environmental pollution is a significant goal nowadays. Phytoextraction, as remediation technique is widely used, but during the process, the heavy metal content of the biomass grown on these sites special treatment and disposal techniques are required, for example liquid extraction, direct disposal, composting, and combustion. These processes are discussed in this review in economical and environmental aspects. The following main properties are analyzed: form and harmful element content of remains, utilization of the main and byproducts, affect to the environment during the treatment and disposal. The thermal treatment (combustion, gasification) of contaminated biomass provides a promising alternative disposal option, because the energy production affects the rate of return, and the harmful elements are riched in a small amount of solid remains depending on the ash content of the plant (1-2%). The biomass combustion technology is a wildely used energy production process in residential and industrial scale, but the ordinary biomass firing systems are not suited to burn this type of fuel without environmental risk. Copyright © 2016 Elsevier Ltd. All rights reserved.

Psychosocial Research on the International Space Station: Special Privacy Considerations

Science.gov (United States)

Kanas, N.; Salnitskiy, V.; Ritsher, J.; Grund, E.; Weiss, D.; Gushin, V.; Kozerenko, O.

Conducting psychosocial research with astronauts and cosmonauts requires special privacy and confidentiality precautions due to the high profile nature of the subject population and to individual crewmember perception of the risks inherent in divulging sensitive psychological information. Sampling from this small population necessitates subject protections above and beyond standard scientific human subject protocols. Many of these protections have relevance for psychosocial research on the International Space Station. In our previous study of psychosocial issues involving crewmembers on the Mir space station, special precautions were taken during each phase of the missions. These were implemented in order to gain the trust necessary to ameliorate the perceived risks of divulging potentially sensitive psychological information and to encourage candid responses. Pre-flight, a standard confidentiality agreement was provided along with a special layman's summary indicating that only group-level data would be presented, and subjects chose their own ID codes known only to themselves. In-flight, special procedures and technologies (such as encryption) were employed to protect the data during the collection. Post-flight, an analytic strategy was chosen to further mask subject identifiers, and draft manuscripts were reviewed by the astronaut office prior to publication. All of the eligible five astronauts and eight cosmonauts who flew joint US/Russian missions on the Mir were successfully recruited to participate, and their data completion rate was 76%. Descriptive analyses of the data indicated that there was sufficient variability in all of the measures to indicate that thoughtful, discriminating responses were being provided (e.g., the full range of response options was used in 63 of the 65 items of the Profile of Mood States measure, and both true and false response options were used in all 126 items of the Group Environment and the Work Environment measures). This

Application of Bayesian network methodology to the probabilistic risk assessment of nuclear waste disposal facility

International Nuclear Information System (INIS)

Lee, Chang Ju

2006-02-01

The scenario in a risk analysis can be defined as the propagating feature of specific initiating event which can go to a wide range of undesirable consequences. If one takes various scenarios into consideration, the risk analysis becomes more complex than do without them. A lot of risk analyses have been performed to actually estimate a risk profile under both uncertain future states of hazard sources and undesirable scenarios. Unfortunately, in case of considering some stochastic passive systems such as a radioactive waste disposal facility, since the behaviour of future scenarios is hardly predicted without special reasoning process, we cannot estimate their risk only with a traditional risk analysis methodology. Moreover, it is believed that the sources of uncertainty at future states can be reduced pertinently by setting up dependency relationships interrelating geological, hydrological, and ecological aspects of the site with all the scenarios. It is then required current methodology of uncertainty analysis of the waste disposal facility be revisited under this belief. In order to consider the effects predicting from an evolution of environmental conditions of waste disposal facilities, this study proposes a quantitative assessment framework integrating the inference process of Bayesian network to the traditional probabilistic risk analysis. In this study an approximate probabilistic inference program for the specific Bayesian network developed and verified using a bounded-variance likelihood weighting algorithm. Ultimately, specific models, including a Monte-Carlo model for uncertainty propagation of relevant parameters, were developed with a comparison of variable-specific effects due to the occurrence of diverse altered evolution scenarios (AESs). After providing supporting information to get a variety of quantitative expectations about the dependency relationship between domain variables and AESs, this study could connect the results of probabilistic

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.)

Progress report on disposal concept for TRU waste in Japan

International Nuclear Information System (INIS)

2000-03-01

The object of this report is to contribute towards establishing a national TRU waste disposal program by integrating the results of research and development work carried out by JNC and the electricity utilities and summarizing the findings concerning safe methods for TRU waste disposal. The report consists of 5 chapters: the first describes the boundary conditions for the review of the TRU waste disposal concept (including geological conditions) and the basic concept adopted; the second describes the generation and characteristics of TRU waste and the third outlines the disposal technology; the fourth gives the key of the safety assessment and the fifth presents the conclusions of the report and lists issues for future consideration. The geological environment of Japan is simply classified into crystalline and sedimentary rock types (in terms of groundwater flow properties and rock strength) and a set of target conditions/properties for each rock type is then established. Based on this, a case which represents the basis for performance assessment (the reference case) will be defined. Alternatives to the reference case are studied to investigate the flexibility of the disposal concept. Under the conditions assumed in this study, the perturbing events considered showed no significant effects on the dose at the 100 meter evaluation point, owing to the relatively high efficiency of the natural barrier. However, the significant effect of these events on nuclide from the EBS shows that, in the case of a less efficient natural barrier, their effects could influence resulting dose. (S.Y.)

Presentation of the project Thermal processes with energy recovery for sludge and special or hazardous waste disposal

International Nuclear Information System (INIS)

Mininni, G.; Passino, R.

2001-01-01

Main results obtained in the framework of the project Thermal processes with energy recovery for sludge and special waste (also hazardous) disposal granted for 2.16 M Euro by the Italian Ministry of Education through Structural Funds are reported. This project is subdivided into the following four main sub projects: combustion of hazardous sludges on a demonstrative plant; combustion of sludges in fluidized bed reactors on pilot and laboratory scale; set up of a flue gas sampling device at high temperature; fluid dynamic modelling of combustion. Original and interesting results were produced mainly connected with the following aspects: combined incineration of sewage and hazardous sludges appeared to be reliable considering that gaseous emissions did not show any deterioration following the addition of chlorinated hydrocarbons to sewage sludge. Gaseous emissions were found to be not conform with the standards only in very few cases generally not linked with critical conditions: polynuclear aromatic hydrocarbons (PAHs) were found to be a reliable parameter for emissions monitoring considering that they are produced in abundance following up set conditions due to a temperature decline or an insufficient oxygen supply; the very stringent limit at the emissions of 0.1 ng/m 3 for dioxins and furans (TE) can be respected in the most of the cases but this monitoring is very complex, time consuming and expensive. Sampling and extraction errors might considerably impact the measured value, which is much more dependent on the conditions inside the recovery boiler rather than on the combustion efficiency; metals are enriched onto the fly ashes produced in the tests carried out by rotating drum furnace more than in the tests by fluidized bed furnace; after burning chamber mode of operation did not display a direct influence on the emissions; incineration tests carried out on reduced pilot scale have shown a total absence of fragmentation during volatilisation while particulate

2005 dossier: granite. Tome: architecture and management of the geologic disposal; Dossier 2005: granite. Tome architecture et gestion du stockage geologique

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

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.)

Heat generation and heating limits for the IRUS LLRW disposal facility

International Nuclear Information System (INIS)

Donders, R.E.; Caron, F.

1995-10-01

Heat generation from radioactive decay and chemical degradation must be considered when implementing low-level radioactive waste (LLRW) disposal. This is particularly important when considering the management of spent radioisotope sources. Heating considerations and temperature calculations for the proposed IRUS (Intrusion Resistant Underground Structure) near-surface disposal facility are presented. Heat transfer calculations were performed using a finite element code with realistic but somewhat conservative heat transfer parameters and environmental boundary conditions. The softening-temperature of the bitumen waste-form (38 deg C) was found to be the factor that limits the heat generation rate in the facility. This limits the IRUS heat rate, assuming a uniform source term, to 0.34 W/m 3 . If a reduced general heat-limit is considered, then some higher-heat packages can be accepted with restrictions placed on their location within the facility. For most LLRW, heat generation from radioactive decay and degradation are a small fraction of the IRUS heating limits. However, heating restrictions will impact on the disposal of higher-activity radioactive sources. High activity 60 Co sources will require decay-storage periods of about 70 years, and some 137 Cs will need to bed disposed of in facilities designed for higher-heat waste. (author). 21 refs., 8 tabs., 2 figs

Evaluation on radioactive waste disposal amount of Kori Unit 1 reactor vessel considering cutting and packaging methods

International Nuclear Information System (INIS)

Choi, Yu Jong; Lee, Seong Cheol; Kim, Chang Lak

2016-01-01

Decommissioning of nuclear power plants has become a big issue in South Korea as some of the nuclear power plants in operation including Kori unit 1 and Wolsung unit 1 are getting old. Recently, Wolsung unit 1 received permission to continue operation while Kori unit 1 will shut down permanently in June 2017. With the consideration of segmentation method and disposal containers, this paper evaluated final disposal amount of radioactive waste generated from decommissioning of the reactor pressure vessel in Kori unit 1 which will be decommissioned as the first in South Korea. The evaluation results indicated that the final disposal amount from the top and bottom heads of the reactor pressure vessel with hemisphere shape decreased as they were cut in smaller more effectively than the cylindrical part of the reactor pressure vessel. It was also investigated that 200 L and 320 L radioactive waste disposal containers used in Kyung-Ju disposal facility had low payload efficiency because of loading weight limitation

Legal provisions concerning the handling and disposal of radioactive waste in international and national law

International Nuclear Information System (INIS)

Bischof, W.

1980-01-01

A short survey is given on the situation of international legislation concerning radioactive waste handling and disposal. There are special rules on the disposal of nuclear waste in a number of conventions (Geneva 1958, London 1972, Helsinki 1974, Paris 1974, Barcellone 1976) on the protection of the marine environment and of the high sea against pollutions. In 1974 and 1978, the International Atomic Energy Agency made further recommendations concerning radioactive wastes referred to in the London Convention. In 1977, the Organisation for Economic Cooperation and Development also set up within its Nuclear Energy Agency (NEA) a multilateral consultation and surveillance mechanism for the sea-dumping of radioactive waste. The NEA has since published recommendations on the sea-dumping of radioactive waste. In 1975, it was agreed to abide by the Antarctic Treaty of 1959 not to dispose any nuclear waste on the Antarctic Region. There is at present no absolute prohibition of radioactive waste disposal in outer space but the Member States of the United Nations are responsible for such activities. As regards national legislation, the legal provisions for 13 different countries on radioactive waste disposal are listed. (UK)

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.)

Evaluation of alternatives for high-level and transuranic radioactive- waste disposal standards

International Nuclear Information System (INIS)

Klett, R.D.; Gruebel, M.M.

1992-12-01

The remand of the US Environmental Protection Agency's long-term performance standards for radioactive-waste disposal provides an opportunity to suggest modifications that would make the regulation more defensible and remove inconsistencies yet retain the basic structure of the original rule. Proposed modifications are in three specific areas: release and dose limits, probabilistic containment requirements, and transuranic-waste disposal criteria. Examination of the modifications includes discussion of the alternatives, demonstration of methods of development and implementation, comparison of the characteristics, attributes, and deficiencies of possible options within each area, and analysis of the implications for performance assessments. An additional consideration is the impact on the entire regulation when developing or modifying the individual components of the radiological standards

Sea transport of used nuclear fuel and radiactive disposals to a Swedish central store

International Nuclear Information System (INIS)

1977-10-01

Sea transport of used nuclear fuel and radioactive disposals to a Swedish central store. A vessel for transporting used nuclear fuel and radioactive disposals from the power stations at Ringhals, Barsebaeck, Simpevarp and Forsmark to a central store has been projected. Safety aspects, technical and economical aspects have been taken into consideration with regard to the actual volume of goods to be transported. Three different types of vessels are presented and a specification is given for the main alternative. A safety study of the main alternative is shown, regarding collision safety, fire risks and fire extinguishing equipment. (author)

Technical and economic evaluation of controlled disposal options for very low level radioactive wastes

International Nuclear Information System (INIS)

Robinson, P.J.; Vance, J.N.

1990-08-01

Over the past several years, there has been considerable interest by the nuclear industry in the Nuclear Regulatory Commission (NRC) explicitly defined an activity level in plant waste materials at which the radiological impacts would be so low as to be considered Below Regulatory Concern (BRC). In January 1989, Electric Power Research Institute (EPRI) completed an extensive industry research effort to develop the technical bases for establishing criteria for the disposal of very low activity wastes in ordinary disposal facilities. The Nuclear Management and Resources Council (NUMARC), with assistance from the Edison Electric Institute (EEI) and the Electric Power Research Institute (EPRI), drafted a petition titled: ''Petition for Rulemaking Regarding Disposal of Below Regulatory Concern Radioactive Wastes from Commercial Nuclear Power Plants.'' Subsequent to the industry making a final decision for submittal of the drafted BRC petition, EPRI was requested to evaluate the technical and economic impact of six BRC options. These options are: take no action in pursuing a BRC waste exemption, petition the NRC for authorization to disposal of any BRC waste in any ordinary disposal facility, limit disposal of BRC waste to the nuclear power plant site, limit disposal of BRC waste to the nuclear power plant site and other utility owned property, petition for a mixed waste exemption, and petition for single waste stream exemptions in sequence (i.e. soil, followed by sewage sludge, etc.). The petition and technical bases were written to support the disposal of any BRC waste type in any ordinary disposal facility. These documents do not provide all of the technical and economic information needed to completely assessment the BRC options. This report provides the technical and economic basis for a range of options concerning disposal of very low activity wastes. 3 figs., 20 tabs

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.

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)

ICRP recommendations and the safe disposal of radioactive waste

International Nuclear Information System (INIS)

Webb, G.A.M.; Barraclough, I.M.

1991-01-01

There are some special difficulties in setting up and applying radiological protection principle to the disposal of solid radioactive wastes. These were recognized by the International Commission on Radiological Protection (ICRP). One difficulty is the uncertain or probabilistic nature of some of the events or processes that could occur and affect the integrity of a waste repository. The other feature of solid waste disposal that causes difficulty is the length of time period of concern. The practical problem is the difficulties in predicting future conditions and in making the useful estimate of long term radiation impact with sufficient confidence. In this paper, the proposals made by the ICRP to deal with the above difficulties are briefly reviewed. Some suggestions are made as to how the criteria might be clarified, and the necessary calculation made to match the criteria. The reappraisal of the criteria for assessing the radiological safety of waste repositories is needed. (K.I.)

Analysis of heat and mass transfer in sub-seabed disposal of nuclear waste

International Nuclear Information System (INIS)

Hickox, C.E.; Gartling, D.K.; McVey, D.F.; Russo, A.J.; Nuttall, H.E.

1980-01-01

A mathematical basis is developed for the prediction of thermal and radionuclide transport in marine sediments. The theory is applied to the study of radioactive waste disposal by emplacement, in specially designed containers, well below the sediment/water interface. Numerical results are obtained for a specified model problem through use of two computer programs designed primarily for the analysis of waste disposal problems. One program (MARIAH) provides descriptions of the temperature and velocity fields induced by the presence of a container of thermally active nuclear waste. A second program (IONMIG), which utilizes the results of the thermal analysis, is used to provide predictions for the migration of four representative radionuclides: 239 Pu, 137 Cs, 129 I, and 99 Tc

Arsenic waste management: a critical review of testing and disposal of arsenic-bearing solid wastes generated during arsenic removal from drinking water.

Science.gov (United States)

Clancy, Tara M; Hayes, Kim F; Raskin, Lutgarde

2013-10-01

Water treatment technologies for arsenic removal from groundwater have been extensively studied due to widespread arsenic contamination of drinking water sources. Central to the successful application of arsenic water treatment systems is the consideration of appropriate disposal methods for arsenic-bearing wastes generated during treatment. However, specific recommendations for arsenic waste disposal are often lacking or mentioned as an area for future research and the proper disposal and stabilization of arsenic-bearing waste remains a barrier to the successful implementation of arsenic removal technologies. This review summarizes current disposal options for arsenic-bearing wastes, including landfilling, stabilization, cow dung mixing, passive aeration, pond disposal, and soil disposal. The findings from studies that simulate these disposal conditions are included and compared to results from shorter, regulatory tests. In many instances, short-term leaching tests do not adequately address the range of conditions encountered in disposal environments. Future research directions are highlighted and include establishing regulatory test conditions that align with actual disposal conditions and evaluating nonlandfill disposal options for developing countries.

A new look at the economic disposal of contaminated aerosol filters

International Nuclear Information System (INIS)

Sinhuber, D.; Stiehl, H.H.; Schroth, W.

1977-01-01

HEPA filter elements loaded with radioactive aerosols represent a large percentage of the radioactive waste of nuclear plants. The HEPA filter elements used at present in air filter units are not suitable to an economic disposal and space-saving final storage on account of their construction. New concepts for HEPA filters are necessary from the point of view of waste disposal. The criteria of these new designs are as follows: reduction of space required for HEPA filters used at the same or even increased flow rates and with the same efficiency; essentially smaller dimensions of HEPA filters for storage in waste containers; removal without contamination, volume reduction (without contamination) for disposal of the HEPA filters; smallest possible volume of the HEPA filters after processing for final storage. The construction of HEPA filters as a result of the requirements mentioned above and taking into consideration the present stage of technology is explained. The advantages of such construction with regard to the criteria mentioned before are presented in comparison with the HEPA filters at present in use

Environmental risk assessment: its contribution to criteria development for HLW disposal

International Nuclear Information System (INIS)

Smith, G.M.; Little, R.H.; Watkins, B.M.

1999-01-01

Principles for radioactive waste management have been provided by the International Atomic Energy Agency in Safety Series No.111-F, which was published in 1995. This has been a major step forward in the process of achieving acceptance for proposals for disposal of radioactive waste, for example, for High Level Waste disposal in deep repositories. However, these principles have still to be interpreted and developed into practical radiation protection criteria. Without prejudicing final judgements on the acceptability of waste proposals, an important aspect is that practical demonstration of compliance (or the opposite) with these criteria must be possible. One of the IAEA principles requires that radioactive waste shall be managed in such a way as to provide an acceptable level of protection of the environment. There has been and continues to be considerable debate as to how to demonstrate compliance with such a principle. This paper briefly reviews the current status and considers how experience in other areas of environmental protection could contribute to criteria development for HLW disposal

The Potential for Criticality Following Disposal of Uranium at Low-Level-Waste Facilities. Containerized Disposal

International Nuclear Information System (INIS)

Colten-Bradley, V.A.; Hopper, C.M.; Parks, C.V.; Toran, L.E.

1999-01-01

The purpose of this study was to evaluate whether or not fissile uranium in low-level-waste (LLW) facilities can be concentrated by hydrogeochemical processes to permit nuclear criticality. A team of experts in hydrology, geology, geochemistry, soil chemistry, and criticality safety was formed to develop and test some reasonable scenarios for hydrogeochemical increases in concentration of special nuclear material (SNM) and to use these scenarios to aid in evaluating the potential for nuclear criticality. The team's approach was to perform simultaneous hydrogeochemical and nuclear criticality studies to (1) identify some possible scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) model groundwater transport and subsequent concentration increase via precipitation of uranium, and (3) evaluate the potential for nuclear criticality resulting from potential increase in uranium concentration over disposal limits. The analysis of SNM was restricted to 235 U in the present scope of work. The work documented in this report indicates that the potential for a criticality safety concern to arise in an LLW facility is extremely remote, but not impossible. Theoretically, conditions that lead to a potential criticality safety concern might arise. However, study of the hydrogeochemical mechanisms, the associated time frames, and the factors required for an actual criticality event indicate that proper emplacement of the SNM at the site can eliminate practical concerns relative to the occurrence and possible consequences of a criticality event

Preliminary risk assessment for nuclear waste disposal in space. Volume I. Executive summary of technical report

International Nuclear Information System (INIS)

Rice, E.E.; Denning, R.S.; Friedlander, A.L.

1982-01-01

Three major conclusions come from this preliminary risk assessment of nuclear waste disposal in space. Preliminary estimates of space disposal risk are low, even with the estimated uncertainty bounds. If calculated mined geologic repository (MGR) release risks remain low, and the EPA requirements continue to be met, then no additional space disposal study effort is warranted. If risks perceived by the public are significant in the acceptance of mined geologic repositories, then consideration of space disposal as an MGR complement is warranted. As a result of this study, the following recommendations are made to NASA and the US DOE: During the continued evaluation of the mined geologic repository risk over the years ahead by DOE, if any significant increase in the calculated health risk is predicted for the MGR, then space disposal should be reevaluated at that time. The risks perceived by the public for the MGR should be evaluated on a broad basis by an independent organization to evaluate acceptance. If, in the future, MGR risks are found to be significant due to some presently unknown technical or social factor, and space disposal is selected as an alternative that may be useful in mitigating the risks, then the following space disposal study activities are recommended: improvement in chemical processing technology for wastes; payload accident response analysis; risk uncertainty analysis for both MGR and space disposal; health risk modeling that includes pathway and dose estimates; space disposal cost modeling; assessment of space disposal perceived (by public) risk benefit; and space systems analysis supporting risk and cost modeling

Nuclear waste disposal: alternatives to solidification in glass proposed

International Nuclear Information System (INIS)

Kerr, R.A.

1979-01-01

More than a quarter-million cubic meters of liquid radioactive wastes are now being held at government installations awaiting final disposal. During the past 20 years, the disposal plan of choice has been to incorporate the 40 to 50 radioactive elements dissolved in liquid wastes into blocks of glass, seal the glass in metal canisters, and insert the canisters into deep, geologically stable salt beds. Over the last few years, some geologists and materials scientists have become concerned that perhaps not enough is known yet about the interaction of waste, container, and salt (or any rock) to have a reasonable assurance that the hazardous wastes will be contained successfully. The biggest advantage of glass at present is the demonstrated practicality of producing large, highly radioactive blocks of it. The frontrunner as a successor to glass is ceramics, which are nonmetallic crystalline materials formed at high temperature, such as chinaware or natural minerals. An apparent advantage of ceramics is that they already have an ordered atomic structure, whose properties can be tailored to a particular waste element and to conditions of a specific disposal site. A ceramic tailored for waste disposal called supercalcine-ceramic has been developed. It was emphasized that the best minerals for waste solidification may be those that have proved most stable under natural conditions over geologic time. Disadvantage to ceramics are radiation damage and transmutation. However, it is now obvious that some ceramics are more stable than glass under certain conditions. Metal-encapsulated ceramic, called cermet, is being developed as a waste form. Cermets are considerably more resistant at 100 0 C than a borosilicate waste glass. Researchers are now testing prospective waste forms under the most extreme conditions that might prevail in a waste disposal site

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

Economic and ecological optimal strategies of management of the system of regional solid waste disposal

Directory of Open Access Journals (Sweden)

Samoylik Marina S.

2014-01-01

Full Text Available The article develops an economic and ecological model of optimal management of the system of solid waste disposal at the regional level, identifies its target functions and forms optimisation scenarios of management of this sphere with theoretically optimal parameters’ values. Based on the model of management of the sphere of solid waste disposal the article forms an algorithm of identification of optimal managerial strategies and mechanisms of their realisation, which allows solution of the set tasks of optimisation of development of the sphere of solid waste disposal at a given set of values and parameters of the state of the system for a specific type of life cycle of solid waste and different subjects of this sphere. The developed model has a number of feasible solutions and, consequently, offers selection of the best of them with consideration of target functions. The article conducts a SWOT analysis of the current state of solid waste disposal in the Poltava region and identifies a necessity of development of a relevant strategy on the basis of the developed economic and ecological model with consideration of optimisation of mutually opposite criteria: ecological risk for the population from the sphere of solid waste disposal and total expenditures for this sphere functioning. The article conducts modelling of this situation by basic (current situation and alternative scenarios and finds out that, at this stage, it is most expedient to build in the region four sorting lines and five regional solid waste grounds, while expenditures on this sphere are UAH 62.0 million per year, income from secondary raw material sales – UAH 71.2 per year and reduction of the ecological risk – UAH 13 million per year.

Human intruder dose assessment for deep geological disposal

International Nuclear Information System (INIS)

Smith, G. M.; Molinero, J.; Delos, A.; Valls, A.; Conesa, A.; Smith, K.; Hjerpe, T.

2013-07-01

For near-surface disposal, approaches to assessment of inadvertent human intrusion have been developed through international cooperation within the IAEA's ISAM programme. Other assessments have considered intrusion into deep geological disposal facilities, but comparable international cooperation to develop an approach for deep disposal has not taken place. Accordingly, the BIOPROTA collaboration project presented here (1) examined the technical aspects of why and how deep geological intrusion might occur; (2) considered how and to what degree radiation exposure would arise to the people involved in such intrusion; (3) identified the processes which constrain the uncertainties; and hence (4) developed and documented an approach for evaluation of human intruder doses which addresses the criteria adopted by the IAEA and takes account of other international guidance and human intrusion assessment experience. Models for radiation exposure of the drilling workers and geologists were developed and described together with compilation of relevant input data, taking into account relevant combinations of drilling technique, geological formation and repository material. Consideration has been given also to others who might be exposed to contaminated material left at the site after drilling work has ceased. The models have been designed to be simple and stylised, in accordance with international recommendations. The set of combinations comprises 58 different scenarios which cover a very wide range of human intrusion possibilities via deep drilling. (orig.)

Radiological assessment of the consequences of the disposal of high-level radioactive waste in subseabed sediments

International Nuclear Information System (INIS)

de Marsily, G.; Behrendt, V.; Ensminger, D.A.

1987-01-01

The radiological assessment of the seabed option consists in estimating the detriment to man and to the environment that could result from the disposal of high-level waste (HLW) within the seabed sediments in deep oceans. The assessment is made for the high-level waste (vitrified glass) produced by the reprocessing of 10 5 tons of heavy metal from spent fuel, which represents the amount of waste generated by 3333 reactor-yr of 900-MW(electric) reactors, i.e., 3000 GW(electric) x yr. The disposal option considered is to use 14,667 steel penetrators, each of them containing five canisters of HLW glass (0.15 m 3 each). These penetrators would reach a depth of 50 m in the sediments and would be placed at an average distance of 180 m from each other, requiring a disposal area on the order of 22 x 22 km. Two such potential disposal areas in the Atlantic Ocean were studied, Great Meteor East (GME) and South Nares Abyssal Plains (SNAP). A special ship design is proposed to minimize transportation accidents. Approximately 100 shipments would be necessary to dispose of the proposed amount of waste. The results of this radiological assessment seem to show that the disposal of HLW in subseabed sediments is radiologically a very acceptable option

NWTRB special report to congress and the Secretary of Energy

International Nuclear Information System (INIS)

1993-03-01

The Nuclear Waste Technical Review Board (the Board) was created by Congress in 1987 to review the scientific and technical validity of the Department of Energy's (DOE) civilian radioactive waste management program. The goal of the DOE's program is to design and develop a system to manage and safely dispose of the spent nuclear fuel being produced at the nation's 108 commercial nuclear power plants along with some high-level reprocessing wastes from defense-related activities. During its review of the program, the Board has witnessed considerable progress, especially in site characterization and data collection at Yucca Mountain, and, given existing data, this NWTRB Special Report to Congress and the Secretary of Energy briefly outlines three of the Board's major concerns: (1) the program's unrealistic deadlines, (2) the need for an integrated overall waste management plan, and (3) the effectiveness of program management. The Board believes that these concerns should be addressed immediately, concurrent with ongoing site-characterization work, to ensure that the program has a strong technical and scientific base and to facilitate program progress

The land impact associated with the disposal of radioactive wastes

International Nuclear Information System (INIS)

Redmond, I.G.

1983-01-01

At present, the only land being utilized for the storage of radioactive wastes in Canada is at the sites of nuclear power generating stations, for high- and low-level wastes, and the land adjacent to uranium mines and mills in the case of tailings and the land in the vicinity of the uranium refinery in Port Hope. Existing storage sites for high- and low-level wastes do not occupy large amounts of land, since the amount of materials is relatively small. Uranium mine tailings, however, need hundreds of hectares of land. In addition to land directly utilized for the storage of the wastes, there may be a need for future buffer zones to separate them from adjoining land uses once a method of permanent disposal is decided. Any land utilized for the disposal of the wastes is likely to be unsuitable for other uses for anywhere from a few years to several thousand years, depending on the waste type occupying the land. Clearly, use of land for the storage and disposal of radioactive wastes may influence it beyond site boundaries and restrict its usage for other purposes for some considerable time to come

Basic factors for the treatment and disposal of radioactive wastes

International Nuclear Information System (INIS)

1967-01-01

This manual discusses factors such as type of waste, legislation, climate, location and availability of materials, equipment and services, etc., which must be taken into account before the preliminary evaluation can be made to decide which treatment and disposal methods should be further investigated. As an aid in selecting the most suitable type of waste management system, a questionnaire has been prepared drawing attention to those factors which should be taken into consideration.

Modelling the long-term evolution of geological radwaste disposal facilities

International Nuclear Information System (INIS)

Dames and Moore International Twickenham

1990-01-01

The report aims to answer questions such as How much do we know about environmental change, How does it apply to the performance assessment of radioactive waste disposal sites and What methods are available for incorporating considerations of environmental change into performance assessment. The document comprises two parts: Part 1 presents a review of the status of research into the effects of long-term environmental changes on deep land disposal facilities for radioactive waste, and then outlines a general specification for modelling these efforts; Part 2 presents background research on permafrost evolution and its potential effects on groundwater systems. Although much work exists on the growth of ice in soils, at shallow levels, relatively little is known about the growth of deep permafrost. A large appendix is devoted to the theoretical work on permafrost growth and its conclusions

Special Analysis: Atmospheric Dose Resulting from the Release of C14 from Reactor Moderator Deionizers in a Disposal Environment

International Nuclear Information System (INIS)

Hiergesell, Robert A.; Swingle, Robert F.

2005-01-01

The proposed action of disposing of 52 moderator deionizer vessels within the ILV was evaluated in this SA. In particular, a detailed analysis of the release of 14 C via the atmospheric pathway was conducted for these vessels since the major concern has been the nearly 20 Ci of 14 C that is associated with each vessel. The more rigorous evaluation of the atmospheric pathway for 14 C included incorporation of new information about the chemical availability of 14 C when disposed in a grout/cement encapsulation environment, as will be the case in the ILV. This information was utilized to establish the source term for a 1-D numerical model to simulate the diffusion of 14 CO 2 from the ILV Waste Zone to the land surface. The results indicate a peak surface emanation rate from the entire ILV of 1.42E-08 Ci/yr with an associated dose of only 3.83E-05 mrem/yr to the Maximally Exposed Individual (MEI) at 100m. The fact that the atmospheric pathway exposure for 14 C is controlled by chemical solubility limits for 14 C between the solid waste, pore water and pore vapor within the disposal environment rather than the absolute inventory suggests that the establishment of specific facility limits is inappropriate. With the relaxation of the atmospheric pathway restriction, the groundwater pathway becomes the more restrictive in terms of disposing 14 C or 14 C KB within the ILV. Since the resin-based 14 C of the 52 moderator deionizer vessels is highly similar to the 14 C KB waste form, the inventory from the 52 deionizer vessels is compared against the groundwater limits for that waste form. The small groundwater pathway fraction (1.14E-05) calculated for the proposed inventory of the 52 moderator deionizer vessels indicates that the proposed action will have an insignificant impact with respect to possible exposures via the groundwater pathway. This investigation recommends that there be no ILV Atmospheric pathway limit for 14 C and 14 C KB . Further, in the absence of an

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

Typing operations manual and disposal of fixed assets: directions of improvement of accounting

Directory of Open Access Journals (Sweden)

I.M. Vygivska

2016-09-01

Full Text Available The lack of studies on the structure of business operations for the operation and disposal of fixed assets leads to undeveloped organizational and methodological provisions of the relevant accounting operations. In particular, the lack of comprehensive understanding of these operations can not account for the loss of alternatives and economic benefits from the use of fixed assets in various areas of economic activity. To streamline the organizational and methodological approaches to accounting of fixed assets, and monitor the effectiveness of the use and preservation of the property of the owner of the enterprise, and according to the analysis of literary sources showing a considerable amount of controversy in the existing approach of the authors, to characterize the operations manual and the disposal of fixed assets, the article suggests typing operations, exploitation and disposal of fixed assets. The main types of these operations include: 1 operation – storage, use, maintenance, repair and improvement; 2 disposal - sale, free transfer, exchange, cancellation due to moral and physical deterioration, capital contribution, financial lease, the installation of shortage, the transfer in payment of debt, the loss resulting from emergencies.

Special actinide nuclides: Fuel or waste?

International Nuclear Information System (INIS)

Srinivasan, M.; Rao, K.S.; Dingankar, M.V.

1989-01-01

The special actinide nuclides such as Np, Cm, etc. which are produced as byproducts during the operation of fission reactors are presently looked upon as 'nuclear waste' and are proposed to be disposed of as part of high level waste in deep geological repositories. The potential hazard posed to future generations over periods of thousands of years by these long lived nuclides has been a persistent source of concern to critics of nuclear power. However, the authors have recently shown that each and every one of the special actinide nuclides is a better nuclear fuel than the isotopes of plutonium. This finding suggests that one does not have to resort to exotic neutron sources for transmuting/incinerating them as proposed by some researchers. Recovery of the special actinide elements from the waste stream and recycling them back into conventional fission reactors would eliminate one of the stigmas attached to nuclear energy

Radiation protection aspects of waste disposal

International Nuclear Information System (INIS)

Beninson, D.

1992-01-01

Waste disposal, particularly of high level waste and some alpha-waste, involves very long times of isolation from the biosphere. The basic radiation protection requirements of 'optimisation of protection' and 'limitation of individual risk' must be complemented with policy decisions regarding the level of ambition of protection for future individuals and populations. Decisions are also necessary for the risk assessments applicable to different time periods. These assessments include considerable uncertainty and determinations of compliance with regulatory requirements must contemplate a policy for taking account of such uncertainties. The paper deals with 'normal' scenarios and with disruptive events as mechanisms for the return of nuclides to the biosphere, in the framework of the Recommendations of the ICRP. (author)

The disposal of radioactive solvent waste

International Nuclear Information System (INIS)

Dean, B.; Baker, W.T.

1976-01-01

As the use of radioisotope techniques increases, laboratories are faced with the problem of disposing of considerable quantities of organic solvent and aqueous liquid wastes. Incineration or collection by a waste contractor both raise problems. Since most of the radiochemicals are preferentially water soluble, an apparatus for washing the radiochemicals out into water and discharging into the normal drainage system in a high diluted form is described. Despite the disadvantages (low efficiency, high water usuage, loss of solvent in presence of surface active agents, precipitation of phosphors from dioxan based liquids) it is felt that the method has some merit if a suitably improved apparatus can be designed at reasonable cost. (U.K.)

A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

International Nuclear Information System (INIS)

Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

1993-07-01

The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program

Safety standards for near surface disposal and the safety case and supporting safety assessment for demonstrating compliance with the standards

International Nuclear Information System (INIS)

Metcalf, P.

2003-01-01

The report presents the safety standards for near surface disposal (ICRP guidance and IAEA standards) and the safety case and supporting safety assessment for demonstrating compliance with the standards. Special attention is paid to the recommendations for disposal of long-lived solid radioactive waste. The requirements are based on the principle for the same level of protection of future individuals as for the current generation. Two types of exposure are considered: human intrusion and natural processes and protection measures are discussed. Safety requirements for near surface disposal are discussed including requirements for protection of human health and environment, requirements or safety assessments, waste acceptance and requirements etc

The Management System for the Development of Disposal Facilities for Radioactive Waste

International Nuclear Information System (INIS)

2011-01-01

implementation of the management system at each phase of the repository life cycle will contribute towards meeting current repository project requirements and objectives and enhance flexible implementation of changes in the future. As mentioned in both the General Safety Requirements and the Safety Guide on waste disposal, a management system should support the development, implementation and continued enhancement of a pragmatic and strong safety culture, and should promote the adoption of best practices for all waste disposal activities. The design and development of a repository is truly an interdisciplinary activity, involving a range of technical and management issues. The life cycle of a repository extends from hundreds of years for a near surface facility to hundreds of thousands of years for a geological repository. Unlike other nuclear facilities, there are many issues that are unique to disposal facilities and which require special consideration in the development and application of an effective management system that is applicable to a repository development project. The design and development process starts with the compilation of design inputs and culminates with the production of design outputs, which are then transferred and used in subsequent stages of the repository development process. Both design input and output have to be verified, validated and approved before they can be used in subsequent stages of the design process. A project on construction/upgrading of a repository may be divided into interrelated and interdependent processes as a way of planning and managing the project. It is necessary to clearly define and link the project processes, and to integrate them and manage them as a system. The same principles and practices of a management system can be applied as they are relevant to a project's management system. Project management processes include planning, organizing, controlling, reporting and corrective actions.

Addressing ethical considerations about nuclear fuel waste management

International Nuclear Information System (INIS)

Greber, M.A.

1996-01-01

Ethical considerations will be important in making decisions about the long-term management of nuclear fuel waste. Public discussions of nuclear fuel waste management are dominated by questions related to values, fairness, rights and responsibilities. To address public concerns, it is important to demonstrate that ethical responsibilities associated with the current management of the waste are being fulfilled. It is also important to show that our responsibilities to future generations can be met, and that ethical principles will be applied to the implementation of disposal. Canada's nuclear fuel waste disposal concept, as put forward in an Environmental Impact Statement by Atomic Energy of Canada Limited (AECL), is currently under public review by a Federal Environmental Assessment Panel. Following this review, recommendations will be made about the direction that Canada should take for the long-term management of this waste. This paper discusses the ethical principles that are seen to apply to geological disposal and illustrates how the Canadian approach to nuclear fuel waste management can meet the challenge of fulfilling these responsibilities. The author suggests that our ethical responsibilities require that adaptable technologies to site, design, construct, operate decommission and close disposal facilities should de developed. We cannot, and should not, present future generations from exercising control over what they inherit, nor control whether they modify or even reverse today's decisions if that is what they deem to be the right thing to do. (author)

Conditioning of Radioactive Wastes Prior to disposal; Segregation and Repackaging

Energy Technology Data Exchange (ETDEWEB)

Kang, Il Sik; Kim, Ki Hong; Hong, Dae Seok; Lee, Bum Chul [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

We stored several types of radioactive wastes at interim storage facility of KAERI ; the combustible wastes (cloths, decontamination paper and vinyls) from Hanaro multipurpose research reactor, nuclear fuel cycle facility, RI production facility and laboratories, and the non-combustible wastes (metals and glass) dismantled and discarded from the apparatus of laboratories which deteriorated, and also the miscellaneous wastes (spent air-filters). After a segregation of these wastes as the same type, they were treated by using a proper method in order to meet both the national regulation and the waste acceptance criteria of Kyung-ju disposal site. For a safe disposal of waste drums, the waste characterization system including a scaling factor which is hard to measure special radionuclides is established completely. All data of those repackaged drums were input into an ANSIM system so that we could manage them clearly and effectively such like an easy transparent traceability. Through a decontamination of empty drums generated in a repackaging process of the stored drums, these drums can be reused or compressed to reduce their volume reduction for disposal. As a result, the space to store radioactive waste drums are secured more than before, and also the interim storage facility are maintained in a good state. The combustible wastes, which stored at the interim storage facility of KAERI, are managed safely in compliance with the specifications of the national regulations and disposal site. Through the classification and repackage of them, the storage space of drums at RWTF was secured more than before, and the storage facility was kept in a good state, and also the disposal cost of all stored waste drums of KAERI will be reduced due to the reduction of waste volume. Base on the experiences, the non-combustible wastes will be treated soon.

Study of applicable methods on safety verification of disposal facilities and waste packages

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Three subjects about safety verification on the disposal of low level radioactive waste were investigated in FY. 2012. For radioactive waste disposal facilities, specs and construction techniques of covering with soil to prevent possible destruction caused by natural events (e.g. earthquake) were studied to consider verification methods for those specs. For waste packages subject to near surface pit disposal, settings of scaling factor and average radioactivity concentration (hereafter referred to as ''SF'') on container-filled and solidified waste packages generated from Kashiwazaki Kariwa Nuclear Power Station Unit 1-5, setting of cesium residual ratio of molten solidified waste generated from Tokai and Tokai No.2 Power Stations, etc. were studied. Those results were finalized in consideration of the opinion from advisory panel, and publicly opened as JNES-EV reports. In FY 2012, five JNES reports were published and these have been used as standards of safety verification on waste packages. The verification method of radioactive wastes subject to near-surface trench disposal and intermediate depth disposal were also studied. For radioactive wastes which will be returned from overseas, determination methods of radioactive concentration, heat rate and hydrogen generation rate of CSD-C were established. Determination methods of radioactive concentration and heat rate of CSD-B were also established. These results will be referred to verification manuals. (author)

Regulatory approaches in the United States of America for safe management and disposal of long-lived radionuclides

International Nuclear Information System (INIS)

Greeves, J.T.; Bell, M.J.; Nelson, R.A.

1998-01-01

Regulation of the safe management and disposal of commercial, man-made, long-lived radioactive wastes in the United States is the responsibility of the US Nuclear Regulatory Commission (NRC). In some instances, state regulatory authorities have entered into agreements with the NRC to exercise regulatory authority over management and disposal of low-level radioactive wastes and uranium mill tailings within their borders. The legal and regulatory framework employed to achieve safe management and disposal of long-lived radioactive wastes in the US regulatory system is quite detailed, and in many cases the requirements are considerably prescriptive. The NRC has undertaken an initiative to move in the direction of adopting risk-informed, performance-based and risk-informed, less-prescriptive regulations. The current status and future direction of the legal and regulatory framework for management and disposal of commercial long-lived radioactive waste in the US is described. (author)

Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities

International Nuclear Information System (INIS)

1985-01-01

This document provides an overview of basic information related to waste acceptance criteria for disposal in shallow ground and rock cavity repositories, consisting of a discussion of acceptable waste types. The last item includes identification of those waste characteristics which may influence the performance of the disposal system and as such are areas of consideration for criteria development. The material is presented in a manner similar to a safety assessment. Waste acceptance criteria aimed at limiting the radiation exposure to acceptable levels are presented for each pathway. Radioactive wastes considered here are low-level radioactive wastes and intermediate-level radioactive wastes from nuclear fuel cycle operations and applications of radionuclides in research, medicine and industry

Optimalization studies concerning volume reduction and conditioning of radioactive waste in view of storage and disposal (geological disposal into clay)

International Nuclear Information System (INIS)

Dejonghe, P.; Van De Voorde, N.; Bonne, A.

1984-01-01

Volume reduction of low-level and medium-level wastes, and simultaneous optimization of the quality of the conditioned end-product is a major challenge in the management of radioactive wastes. Comments will be given on recent achievements in treatment of non-high-level liquid and solid wastes from power reactors and low-level plutonium contaminated wastes. The latter results can contribute to an overall optimization of a radioactive waste management scheme, including the final disposal of the conditioned materials. Some detailed results will be given concerning volume reduction, decontamination factors, degree of immobilization of the contained radioelements, and cost considerations

Peristaltic pumps for waste disposal

International Nuclear Information System (INIS)

Griffith, G.W.

1992-09-01

Laboratory robots are capable of generating large volumes of hazardous liquid wastes when they are used to perform chemical analyses of metal finishing solutions. A robot at Allied-Signal Inc., Kansas City Division, generates 30 gallons of acid waste each month. This waste contains mineral acids, heavy metals, metal fluorides, and other materials. The waste must be contained in special drums that are closed to the atmosphere. The initial disposal method was to have the robot pour the waste into a collecting funnel, which contained a liquid-sensing valve to admit the waste into the drum. Spills were inevitable, splashing occurred, and the special valve often didn't work well. The device also occupied a large amount of premium bench space. Peristaltic pumps are made to handle hazardous liquids quickly and efficiently. A variable-speed pump, equipped with a quick-loading pump head, was mounted below the robot bench near the waste barrel. The pump inlet tube was mounted above the bench within easy reach of the robot, while the outlet tube was connected directly to the barrel. During operation, the robot brings the waste liquid up to the pump inlet tube and activates the pump. When the waste has been removed, the pump stops. The procedure is quick, simple, inexpensive, safe, and reliable

The surface disposal concept for VLL waste

International Nuclear Information System (INIS)

2011-01-01

Disposal facilities for very-low-level (VLL) waste have been designed to accommodate both residues originating from the decommissioning of nuclear facilities and used components. Those residues have very low specific-activity levels that lie below a few hundreds of becquerels per gram (Bq/g). As for the average activity found in any disposal facility, it never exceeds more than a few tens of becquerels per gram. In that case, waste disposal involves no special processing or conditioning, except for handling requirements or volume-gain purposes. The main barrier against radionuclide dispersion is provided by the geological formation being used for waste disposal. Basic disposal concept The design and construction provisions allow for the optimal operation of the disposal facility without any risk of altering the required safety level. They also ensure a satisfactory containment level for several centuries at the end of the operating lifetime. Hence, the natural materials in their original context constitute a particular advantage for the safety demonstration over the long term. With due account of the nature of VLL waste, their containment envelope (drums, big bags, etc.) has no role in confining radioactivity, but rather in facilitating handling and disposal operations, while protecting operators. Approximately 30% of all waste received at the CSTFA undergo a specific treatment before disposal. Low-density residues (plastics, thermal-insulation materials, etc.) are first compacted by a baling press, then strapped and wrapped in clear plastic-sheet. Another bundle press is used to reduce the volume of scrap metal. Some waste, such as the polluted waters generated on site or the sludges sent by producers, are processed in the solidification and stabilisation unit. Disposal cells are excavated progressively, as needed, directly in the clay formation down to a depth of 8 m and are operated in sequence. Cell design has evolved to maximize the disposal volume, and now

The surface disposal concept for VLL waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

Disposal facilities for very-low-level (VLL) waste have been designed to accommodate both residues originating from the decommissioning of nuclear facilities and used components. Those residues have very low specific-activity levels that lie below a few hundreds of becquerels per gram (Bq/g). As for the average activity found in any disposal facility, it never exceeds more than a few tens of becquerels per gram. In that case, waste disposal involves no special processing or conditioning, except for handling requirements or volume-gain purposes. The main barrier against radionuclide dispersion is provided by the geological formation being used for waste disposal. Basic disposal concept The design and construction provisions allow for the optimal operation of the disposal facility without any risk of altering the required safety level. They also ensure a satisfactory containment level for several centuries at the end of the operating lifetime. Hence, the natural materials in their original context constitute a particular advantage for the safety demonstration over the long term. With due account of the nature of VLL waste, their containment envelope (drums, big bags, etc.) has no role in confining radioactivity, but rather in facilitating handling and disposal operations, while protecting operators. Approximately 30% of all waste received at the CSTFA undergo a specific treatment before disposal. Low-density residues (plastics, thermal-insulation materials, etc.) are first compacted by a baling press, then strapped and wrapped in clear plastic-sheet. Another bundle press is used to reduce the volume of scrap metal. Some waste, such as the polluted waters generated on site or the sludges sent by producers, are processed in the solidification and stabilisation unit. Disposal cells are excavated progressively, as needed, directly in the clay formation down to a depth of 8 m and are operated in sequence. Cell design has evolved to maximize the disposal volume, and now

Conditioning of disused sealed sources in countries without disposal facility: Short term gain - long term pain

International Nuclear Information System (INIS)

Benitez-Navarro, J.C.; Salgado-Mojena, M.

2002-01-01

Owing to the considerable development in managing disused sealed radioactive sources (DSRS), the limited availability of disposal practices for them, and the new recommendations for the use of borehole disposal concept, it was felt that a paper reviewing the existing recommendations could be a starting point of discussion on the retrievability of the sources. Even when no international consensus exists as to an acceptable solution for the challenge of disposal of disused sealed sources, the 'Best Available Technology' for managing most of them, recommended for developing countries, included the cementation of the sources. The waste packages prepared in such a way do not allow any flexibility to accommodate possible future disposal requirements. Therefore, the 'Wait and See' approach could be also recommended for managing not only the sources with long-live radionuclides and high activity, but probably for all kind of existing disused sealed sources. The general aim of the current paper is to identify and review the current recommendations for managing disused sealed sources and to meditate on the most convenient management schemes for disused sealed radioactive sources in Member States without disposal capacities (Latin America, Africa). The risk that cemented DSRS could be incompatible with future disposal requirements was taken into account. (author)

Do systematic reviews on pediatric topics need special methodological considerations?

Science.gov (United States)

Farid-Kapadia, Mufiza; Askie, Lisa; Hartling, Lisa; Contopoulos-Ioannidis, Despina; Bhutta, Zulfiqar A; Soll, Roger; Moher, David; Offringa, Martin

2017-03-06

Systematic reviews are key tools to enable decision making by healthcare providers and policymakers. Despite the availability of the evidence based Preferred Reporting Items for Systematic reviews and Meta-Analysis (PRISMA-2009 and PRISMA-P 2015) statements that were developed to improve the transparency and quality of reporting of systematic reviews, uncertainty on how to deal with pediatric-specific methodological challenges of systematic reviews impairs decision-making in child health. In this paper, we identify methodological challenges specific to the design, conduct and reporting of pediatric systematic reviews, and propose a process to address these challenges. One fundamental decision at the outset of a systematic review is whether to focus on a pediatric population only, or to include both adult and pediatric populations. Both from the policy and patient care point of view, the appropriateness of interventions and comparators administered to pre-defined pediatric age subgroup is critical. Decisions need to be based on the biological plausibility of differences in treatment effects across the developmental trajectory in children. Synthesis of evidence from different trials is often impaired by the use of outcomes and measurement instruments that differ between trials and are neither relevant nor validated in the pediatric population. Other issues specific to pediatric systematic reviews include lack of pediatric-sensitive search strategies and inconsistent choices of pediatric age subgroups in meta-analyses. In addition to these methodological issues generic to all pediatric systematic reviews, special considerations are required for reviews of health care interventions' safety and efficacy in neonatology, global health, comparative effectiveness interventions and individual participant data meta-analyses. To date, there is no standard approach available to overcome this problem. We propose to develop a consensus-based checklist of essential items which

Regulatory decision making in the presence of uncertainty in the context of the disposal of long lived radioactive wastes. Third report of the Working group on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1997-10-01

Plans for disposing of radioactive wastes have raised a number of unique and mostly philosophical problems, mainly due to the very long time-scales which have to be considered. While there is general agreement on disposal concepts and on many aspects of a safety philosophy, consensus on a number of issues remains to be achieved. The IAEA established a subgroup under the International Radioactive Waste Management Advisory Committee (INWAC). The subgroup started its work in 1991 as the ''INWAC Subgroup on Principles and Criteria for Radioactive Waste Disposal''. With the reorganization in 1995 of IAEA senior advisory committees in the nuclear safety area, the title of the group was changed to ''Working Group on Principles and Criteria for Radioactive Waste Disposal''. The working group is intended to provide an open forum for: (1) the discussion and resolution of contentious issues, especially those with an international component, in the area of principles and criteria for safe disposal of waste; (2) the review and analysis of new ideas and concepts in the subject area; (3) establishing areas of consensus; (4) the consideration of issues related to safety principles and criteria in the IAEA's Radioactive Waste Safety Standards (RADWASS) programme; (5) the exchange of information on national safety criteria and policies for radioactive waste disposal. This is the third report of the working group and it deals with the subject of regulatory decision making under conditions of uncertainty which is a matter of concern with respect to disposal of radioactive wastes underground. 14 refs