Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste (Volume 1) Introduction

Energy Technology Data Exchange (ETDEWEB)

R.A. Levich; J.S. Stuckless

2006-09-25

Yucca Mountain in Nevada represents the proposed solution to what has been a lengthy national effort to dispose of high-level radioactive waste, waste which must be isolated from the biosphere for tens of thousands of years. This chapter reviews the background of that national effort and includes some discussion of international work in order to provide a more complete framework for the problem of waste disposal. Other chapters provide the regional geologic setting, the geology of the Yucca Mountain site, the tectonics, and climate (past, present, and future). These last two chapters are integral to prediction of long-term waste isolation.

Geological disposal of high-level radioactive wastes. Historical perspective and contemporary issues

International Nuclear Information System (INIS)

Ahn, Joonhong

2013-01-01

The contemporary concept on the geological disposal of radioactive wastes, the position of Japan in the world stream of geological disposal, and the ideal aspect of the Japanese geological disposal after the Fukushima accident are described. (M.H.)

Radiological protection aspects of geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Matsuzuru, Hideo; Kimura, Hideo

1992-01-01

A high-level radioactive waste, generated at a nuclear fuel reprocessing plant, will be disposed of deep, i.e., several hundred meters, within geological formations, to isolate it from the human environment. Since the waste contains significant amounts of long-lived radionuclides, such as Tc-99, I-129, Cs-135 and transuranic elements, the safety of its disposal, particularly as regards the requirement for the radiological protection of human and his environment even in the far future, is one of the essential subjects of all countries engaged in nuclear power production. The radiological protection system has long been established and applied to regulate radiation exposures to the public associated with a relatively short-term release of radioactive materials, during normal and accidental conditions, from nuclear installations such as a power plant and reprocessing plant. Radioactive waste disposal, which potentially offers a long-term radiological consequence on the public, inevitably produces a specific requirement, from the standpoint of radiological protection, that individuals and populations in the future should be accorded at least a current level of the protection. This requirement has caused a serious debate, among the community of radiological protection, on how to establish radiological protection standards and criteria, and how to establish safety assessment methodologies to demonstrate compliance with them. We have discussed in this paper on specific items such as numerical guides to indicate radiological consequences, time frames over which calculations of the consequences are to be carried out, uncertainties to be involved in the calculations, and safety assessment methodologies. (author)

Key radionuclides and parameters that determine performance of geologic repositories for high-level radioactive wastes

International Nuclear Information System (INIS)

Joonhong Ahn; Atsuyuki Suzuki

1993-01-01

This paper presents results of a mathematical analysis for performance of the engineered barriers of high-level radioactive waste repositories. The main body of the mathematical model developed in this study is mass transport of actinides in a bentonite region. In an analysis of actinide transport, radioactive decay chain and effects of low solubilities must be taken into account. In many previous models for mass transport in engineered barriers including radioactive decay chain, however, boundary conditions at the interface between the waste form and the bentonite region cannot be determined flexibly. In some models, solubility-limited boundary condition is assumed for all the members in a chain. In order to investigate what are key radionuclides and parameters that control performance of engineered barriers of a geologic repository, we must evaluate mass transport with the source boundary condition determined by a detailed analysis on mass transfer at the boundary. In this study, we developed a mathematical model, which can determine whether the inner boundary condition is solubility-limited or congruent release, based on a mathematical analysis for mass transfer at the glass dissolution location, and how long the solubility-limited boundary condition applies. Based on the mathematical model, we point out radionuclides and parameters that have primary influences on the performance of a repository, and investigate a reasonable strategy for coupling geologic disposal and partitioning of those key radionuclides from the standpoint of reducing hazard of geologic disposal. (authors). 4 tabs., 2 figs., 8 refs

Intergenerational ethics of high level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Takeda, Kunihiko [Nagoya Univ., Graduate School of Engineering, Nagoya, Aichi (Japan); Nasu, Akiko; Maruyama, Yoshihiro [Shibaura Inst. of Tech., Tokyo (Japan)

2003-03-01

The validity of intergenerational ethics on the geological disposal of high level radioactive waste originating from nuclear power plants was studied. The result of the study on geological disposal technology showed that the current method of disposal can be judged to be scientifically reliable for several hundred years and the radioactivity level will be less than one tenth of the tolerable amount after 1,000 years or more. This implies that the consideration of intergenerational ethics of geological disposal is meaningless. Ethics developed in western society states that the consent of people in the future is necessary if the disposal has influence on them. Moreover, the ethics depends on generally accepted ideas in western society and preconceptions based on racism and sexism. The irrationality becomes clearer by comparing the dangers of the exhaustion of natural resources and pollution from harmful substances in a recycling society. (author)

Intergenerational ethics of high level radioactive waste

International Nuclear Information System (INIS)

Takeda, Kunihiko; Nasu, Akiko; Maruyama, Yoshihiro

2003-01-01

The validity of intergenerational ethics on the geological disposal of high level radioactive waste originating from nuclear power plants was studied. The result of the study on geological disposal technology showed that the current method of disposal can be judged to be scientifically reliable for several hundred years and the radioactivity level will be less than one tenth of the tolerable amount after 1,000 years or more. This implies that the consideration of intergenerational ethics of geological disposal is meaningless. Ethics developed in western society states that the consent of people in the future is necessary if the disposal has influence on them. Moreover, the ethics depends on generally accepted ideas in western society and preconceptions based on racism and sexism. The irrationality becomes clearer by comparing the dangers of the exhaustion of natural resources and pollution from harmful substances in a recycling society. (author)

Study of heat diffusion in a granitic geologic formation of high level radioactive wastes

International Nuclear Information System (INIS)

Goldstein, S.; Juignet, N.

1980-06-01

Thermal study of granitic underground storage of vitrified high level radioactive wastes in a regular network of shafts and galleries. The aim is to show influence on temperature rise of the geologic formation of main parameters to define the storage zone and to determine the network dimension in function of the rock properties. Two models were studied allowing a rapid variation of geometrical and physical parameters. A numerical method using finite element method or Green functions were used for calculations. Temperatures are determined either for the whole storage site or a unit cell of the lattice [fr

Preliminary study on the three-dimensional geoscience information system of high-level radioactive waste geological disposal

International Nuclear Information System (INIS)

Li Peinan; Zhu Hehua; Li Xiaojun; Wang Ju; Zhong Xia

2010-01-01

The 3D geosciences information system of high-level radioactive waste geological disposal is an important research direction in the current high-level radioactive waste disposal project and a platform of information integration and publishing can be used for the relevant research direction based on the provided data and models interface. Firstly, this paper introduces the basic features about the disposal project of HLW and the function and requirement of the system, which includes the input module, the database management module, the function module, the maintenance module and the output module. Then, the framework system of the high-level waste disposal project information system has been studied, and the overall system architecture has been proposed. Finally, based on the summary and analysis of the database management, the 3D modeling, spatial analysis, digital numerical integration and visualization of underground project, the implementations of key functional modules and the platform have been expounded completely, and the conclusion has been drawn that the component-based software development method should be utilized in system development. (authors)

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

Technical career opportunities in high-level radioactive waste management

International Nuclear Information System (INIS)

1993-01-01

Technical career opportunities in high-level radioactive waste management are briefly described in the areas of: Hydrology; geology; biological sciences; mathematics; engineering; heavy equipment operation; and skilled labor and crafts

What are Spent Nuclear Fuel and High-Level Radioactive Waste?

International Nuclear Information System (INIS)

2002-01-01

Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository

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

International Nuclear Information System (INIS)

Accary, A.

1985-01-01

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

Japan's Siting Process for the Geological Disposal of High-level Radioactive Waste - An International Peer Review

International Nuclear Information System (INIS)

Brassinnes, Stephane; Fabbri, Olivier; Rubenstone, James; Seppaelae, Timo; Siemann, Michael; ); Kwong, Gloria; )

2016-01-01

The Nuclear Energy Agency carried out an independent peer review of Japan's siting process and criteria for the geological disposal of high-level radioactive waste in May 2016. The review concluded that Japan's site screening process is generally in accordance with international practices. As the goal of the siting process is to locate a site - that is both appropriate and accepted by the community - to host a geological disposal facility for high-level radioactive waste, the international review team emphasises in this report the importance of maintaining an open dialogue and interaction between the regulator, the implementer and the public. Dialogue should begin in the early phases and continue throughout the siting process. The international review team also underlines the importance of taking into account feasibility aspects when selecting a site for preliminary investigations, but suggests that it would be inappropriate to set detailed scientific criteria for nationwide screening at this stage. The team has provided extensive advisory remarks in the report as opportunities for improvement, including the recommendation to use clear and consistent terminology in defining the site screening criteria as it is a critical factor in a successful siting process. (authors)

Containers and overpacks for high-level radioactive waste in deep geological disposal. Conditions: French Corrosion Programme

International Nuclear Information System (INIS)

Crusset, D.; Plas, F.; Santarini, G.

2003-01-01

Within the framework of the act of French law dated 31 December, 1991, ANDRA (National Radioactive Waste Management Agency) is responsible for conducting the feasibility study on disposal of reversible and irreversible high-level or long-life radioactive waste in deep geological formations. Consequently, ANDRA is carrying out research on corrosion of the metallic materials envisaged for the possible construction of overpacks for vitrified waste packages or containers for spent nuclear fuel. Low-alloy or unalloyed steels and the passive alloys (Fe-Ni-Cr-Mo) constitute the two families of materials studied and ANDRA has set up a research programme in partnership with other research organisations. The 'broad outlines' of the programme, which includes experimental and modelling operations, are presented. (authors)

Methodology of safety assessment and sensitivity analysis for geologic disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Kimura, Hideo; Takahashi, Tomoyuki; Shima, Shigeki; Matsuzuru, Hideo

1995-01-01

A deterministic safety assessment methodology has been developed to evaluate long-term radiological consequences associated with geologic disposal of high-level radioactive waste, and to demonstrate a generic feasibility of geologic disposal. An exposure scenario considered here is based on a normal evolution scenario which excludes events attributable to probabilistic alterations in the environment. A computer code system GSRW thus developed is based on a non site-specific model, and consists of a set of sub-modules for calculating the release of radionuclides from engineered barriers, the transport of radionuclides in and through the geosphere, the behavior of radionuclides in the biosphere, and radiation exposures of the public. In order to identify the important parameters of the assessment models, an automated procedure for sensitivity analysis based on the Differential Algebra method has been developed to apply to the GSRW. (author)

Bridging nuclear safety, security and safeguards at geological disposl of high level radioactive waste and spent nuclear fuel

International Nuclear Information System (INIS)

Niemeyer, Irmgard; Deissmann, Guido; Bosbach, Dirk

2016-01-01

Findings and recommendations: • Further R&D needed to identify concepts, methods and technologies that would be best suited for the holistic consideration of safety, security and safeguards provisions of geological disposal. • 3S ‘toolbox’, including concepts, methods and technologies for: ■ material accountancy, ■ measurement techniques for spent fuel verification, ■ containment and surveillance, ■ analysis of open source information, ■ environmental sampling and monitoring, ■ continuity of knowledge, ■ design implications. •: Bridging safety, security and safeguards in research funding and research activities related to geological disposal of high-level radioactive waste and spent nuclear fuel.

Using geologic conditions and multiattribute decision analysis to determine the relative favorability of selected areas for siting a high-level radioactive waste repository

International Nuclear Information System (INIS)

Harrison, W.; Edgar, D.E.; Baker, C.H.

1988-05-01

A method is presented for determining the relative favorability of geologically complex areas for isolating high-level radioactive wastes. In applying the method to the northeastern region of the United States, seismicity and tectonic activity were the screening criteria used to divide the region into three areas of increasing seismotectonic risk. Criteria were then used to subdivide the area of lowest seismotectonic risk into six geologically distinct subareas including characteristics, surface-water and groundwater hydrology, potential human intrusion, site geometry, surface characteristics, and tectonic environment. Decision analysis was then used to identify the subareas most favorable from a geologic standpoint for further investigation, with a view to selecting a site for a repository. Three subareas (parts of northeastern Vermont, northern New Hampshire, and western Maine) were found to be the most favorable, using this method and existing data. However, because this study assessed relative geologic favorability, no conclusions should be drawn concerning the absolute suitability of individual subareas for high-level radioactive waste isolation. 34 refs., 7 figs., 20 tabs

NRC regulations for disposal of high-level radioactive wastes in geologic repositories: technical criteria

International Nuclear Information System (INIS)

Martin, J.B.; Bell, M.J.; Regnier, E.P.

1983-01-01

The Nuclear Regulatory Commission is promulgating regulations specifying the technical criteria fo disposal of high-level radioactive wastes in geologic repositories. The proposed rule was published for public comment in July 1981. Public comments have been received and considered by the Commission staff. The Commission will soon approve and publish a revised final rule. While the final rule being considered by the Commission is fundamentally the same as the proposed rule, provisions have been added to permit flexibility in the application of numerical criteria, some detailed design requirements have been deleted, and other changes have been made in response to comments. The rule is consistent with the recently enacted Nuclear Waste Policy Act of 1982

Design concepts of definitive disposal for high level radioactive wastes

International Nuclear Information System (INIS)

Badillo A, V.E.; Alonso V, G.

2007-01-01

It is excessively known the importance about finding a solution for the handling and disposition of radioactive waste of all level. However, the polemic is centered in the administration of high level radioactive waste and the worn out fuel, forgetting that the more important volumes of waste its are generated in the categories of low level wastes or of very low level. Depending on the waste that will be confined and of the costs, several technological modalities of definitive disposition exist, in function of the depth of the confinement. The concept of deep geologic storage, technological option proposed more than 40 years ago, it is a concept of isolation of waste of long half life placed in a deep underground installation dug in geologic formations that are characterized by their high stability and their low flow of underground water. In the last decades, they have registered countless progresses in technical and scientific aspects of the geologic storage, making it a reliable technical solution supported with many years of scientific work carried out by numerous institutions in the entire world. In this work the design concepts that apply some countries for the high level waste disposal that its liberate heat are revised and the different geologic formations that have been considered for the storage of this type of wastes. (Author)

The application of quadtree algorithm for information integration in the high-level radioactive waste geological disposal

International Nuclear Information System (INIS)

Gao Min; Zhong Xia; Huang Shutao

2008-01-01

A multi-source database for high-level radioactive waste geological disposal, aims to promote the information process of the geological of HLW. In the periods of the multi-dimensional and multi-source and the integration of information and applications, it also relates to computer software and hardware, the paper preliminary analysises the data resources Beishan area, Gansu Province. The paper introduces a theory based on GIS technology and methods and open source code GDAL application, at the same time, it discusses the technical methods how to finish the application of the Quadtree algorithm in the area of information resources management system, fully sharing, rapid retrieval and so on. A more detailed description of the characteristics of existing data resources, space-related data retrieval algorithm theory, programming design and implementation of ideas are showed in the paper. (authors)

Strategic program for deep geological disposal of high level radioactive waste in China

International Nuclear Information System (INIS)

Wang Ju

2004-01-01

A strategic program for deep geological disposal of high level radioactive waste in China is proposed in this paper. A '3-step technical strategy': site selection and site characterization-site specific underground research laboratory-final repository, is proposed for the development of China's high level radioactive waste repository. The activities related with site selection and site characterization for the repository can be combined with those for the underground research laboratory. The goal of the strategy is to build China's repository around 2040, while the activities can be divided into 4 phases: 1) site selection and site characterization; 2) site confirmation and construction of underground research laboratory, 3) in-situ experiment and disposal demonstration, and 4) construction of repository. The targets and tasks for each phase are proposed. The logistic relationship among the activities is discussed. It is pointed out that the site selection and site characterization provide the basis for the program, the fundamental study and underground research laboratory study are the key support, the performance assessment plays a guiding role, while the construction of a qualified repository is the final goal. The site selection can be divided into 3 stages: comparison among pre-selected areas, comparison among pre-selected sites and confirmation of the final site. According to this strategy, the final site for China's underground research laboratory and repository will be confirmed in 2015, where the construction of an underground laboratory will be started. In 2025 the underground laboratory will have been constructed, while in around 2040, the construction of a final repository is to be completed

ONDRAF/NIRAS and high-level radioactive waste management in Belgium

International Nuclear Information System (INIS)

Decamps, F.

1993-01-01

The National Agency for Radioactive Waste and Enriched Fissile Materials, ONDRAF/NIRAS, is a public body with legal personality in charge of managing all radioactive waste on Belgian territory, regardless of its origin and source. It is also entrusted with tasks related to the management of enriched fissile materials, plutonium containing materials and used or unused nuclear fuel, and with certain aspects of the dismantling of closed down nuclear facilities. High-level radioactive waste management comprises essentially and for the time being the storage of high-level liquid waste produced by the former EUROCHEMIC reprocessing plant and of high-level and very high-level heat producing waste resulting from the reprocessing in France of Belgian spent fuel, as well as research and development (R and D) with regard to geological disposal in clay of this waste type

Assessment report of research and development on 'geological disposal of high-level radioactive waste' (Interim report)

International Nuclear Information System (INIS)

Notoya, Shin; Shimizu, Kazuhiko; Ota, Kunio; Sasao, Eiji

2010-08-01

Japan Atomic Energy Agency (JAEA) consulted an assessment committee, 'Evaluation Committee of Research and Development (R and D) Activities for Geological Disposal of High-Level Radioactive Waste', for interim assessment of R and D on high-level radioactive waste disposal in accordance with 'General Guideline for Evaluation of Government R and D Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by Japan. In response to JAEA's request, the Committee assessed mainly the progress of the R and D project according to guidelines, which addressed the rationale behind the R and D project, the relevance of the project outcome and the efficiency of the project implementation during the period of the first midterm plan. As a result, the Committee concluded that the progress of the R and D project is satisfactory. In addition, the Committee provided a couple of issues and suggestions to be addressed in the implementation of the project during the period of the second midterm. A CD-ROM is attached as an appendix. (J.P.N.)

Effect of coupling behavior on groundwater flow for geological disposal of radioactive high level waste

International Nuclear Information System (INIS)

Kurikami, Hiroshi; Kobayashi, Akira; Ohnishi, Yuzo; Chijimatsu, Masakazu

2003-01-01

In order to estimate the effects of coupled thermal-hydraulic-mechanical phenomena in near-field for geological disposal of high-level radioactive waste on a vast groundwater flow system, a far-field analysis was simulated based on the results of the simulation of coupled phenomena in near-field using averaged tensor and heat flux. From the results of the coupled analyses of near-field and far-field it was clarified that groundwater flow system was influenced by coupled phenomena in near-field. Moreover, it can be said that groundwater flux into a disposal tunnel is regarded as a complement to safety assessment of a disposal because it strongly correlates with traveling time of groundwater. (author)

Characterizing the proposed geologic repository for high-level radioactive waste at Yucca Mountain, Nevada: hydrology and geochemistry

Science.gov (United States)

Stuckless, John S.; Levich, Robert A.

2012-01-01

This hydrology and geochemistry volume is a companion volume to the 2007 Geological Society of America Memoir 199, The Geology and Climatology of Yucca Mountain and Vicinity, Southern Nevada and California, edited by Stuckless and Levich. The work in both volumes was originally reported in the U.S. Department of Energy regulatory document Yucca Mountain Site Description, for the site characterization study of Yucca Mountain, Nevada, as the proposed U.S. geologic repository for high-level radioactive waste. The selection of Yucca Mountain resulted from a nationwide search and numerous committee studies during a period of more than 40 yr. The waste, largely from commercial nuclear power reactors and the government's nuclear weapons programs, is characterized by intense penetrating radiation and high heat production, and, therefore, it must be isolated from the biosphere for tens of thousands of years. The extensive, unique, and often innovative geoscience investigations conducted at Yucca Mountain for more than 20 yr make it one of the most thoroughly studied geologic features on Earth. The results of these investigations contribute extensive knowledge to the hydrologic and geochemical aspects of radioactive waste disposal in the unsaturated zone. The science, analyses, and interpretations are important not only to Yucca Mountain, but also to the assessment of other sites or alternative processes that may be considered for waste disposal in the future. Groundwater conditions, processes, and geochemistry, especially in combination with the heat from radionuclide decay, are integral to the ability of a repository to isolate waste. Hydrology and geochemistry are discussed here in chapters on unsaturated zone hydrology, saturated zone hydrology, paleohydrology, hydrochemistry, radionuclide transport, and thermally driven coupled processes affecting long-term waste isolation. This introductory chapter reviews some of the reasons for choosing to study Yucca Mountain as a

Characterizing the proposed geologic repository for high-level radioactive waste at Yucca Mountain, Nevada--hydrology and geochemistry

Science.gov (United States)

Stuckless, John S.; Levich, Robert A.

2012-01-01

This hydrology and geochemistry volume is a companion volume to the 2007 Geological Society of America Memoir 199, The Geology and Climatology of Yucca Mountain and Vicinity, Southern Nevada and California, edited by Stuckless and Levich. The work in both volumes was originally reported in the U.S. Department of Energy regulatory document Yucca Mountain Site Description, for the site characterization study of Yucca Mountain, Nevada, as the proposed U.S. geologic repository for high-level radioactive waste. The selection of Yucca Mountain resulted from a nationwide search and numerous committee studies during a period of more than 40 yr. The waste, largely from commercial nuclear power reactors and the government's nuclear weapons programs, is characterized by intense penetrating radiation and high heat production, and, therefore, it must be isolated from the biosphere for tens of thousands of years. The extensive, unique, and often innovative geoscience investigations conducted at Yucca Mountain for more than 20 yr make it one of the most thoroughly studied geologic features on Earth. The results of these investigations contribute extensive knowledge to the hydrologic and geochemical aspects of radioactive waste disposal in the unsaturated zone. The science, analyses, and interpretations are important not only to Yucca Mountain, but also to the assessment of other sites or alternative processes that may be considered for waste disposal in the future. Groundwater conditions, processes, and geochemistry, especially in combination with the heat from radionuclide decay, are integral to the ability of a repository to isolate waste. Hydrology and geochemistry are discussed here in chapters on unsaturated zone hydrology, saturated zone hydrology, paleohydrology, hydrochemistry, radionuclide transport, and thermally driven coupled processes affecting long-term waste isolation. This introductory chapter reviews some of the reasons for choosing to study Yucca Mountain as a

Study on engineering economics of China high-level radioactive waste geological disposal

International Nuclear Information System (INIS)

Qu Jun; Guo Zongzhi; Yang Lirong; Hu Jiang

2012-01-01

In this paper, based on the research and analysis about the repository construction cost of the European, US and Japan, together with the concept design pattern of China's high level radioactive waste repository, the preliminary economic analysis of China is presented. Meanwhile, combining with China's nuclear power development layout and picking-up policy of spent fuel fund, the preliminary measurement concerning the capital resource of high level radioactive waste disposal is implemented, which contribute to the conclusion initiatively that the spent fuel fund could meet the need of the financial demand of disposal cost. (authors)

Conceptual design of the virtual engineering system for high level radioactive waste geological disposal

International Nuclear Information System (INIS)

2000-02-01

The role of Virtual Engineering System for High Level Radioactive Waste Geological Disposal (hereafter the VES) is to accumulate and unify the results of research and development which JNC had been carried out for the completion of the second progress report on a computer system. The purpose and functions of VES with considering the long-term plan for geological disposal in Japan was studied. The analysis between geological environment assessment, safety performance assessment, and engineering technology had not been integrated mutually in the conventional study. The iterative analysis performed by VES makes it possible to analyze natural barrier and engineering barrier more quantitatively for obtaining safety margin and rationalization of the design of a waste repository. We have examined the system functions to achieve the above purpose of VES. Next, conceptual design for codes, databases, and utilities that consist of VES were performed by examining their purpose and functions. The conceptual design of geological environment assessment system, safety performance assessment system, waste repository element database, economical assessment system, investigation support system, quality assurance system, and visualization system are preformed. The whole system configuration, examination of suitable configuration of hardware and software, examination of system implementation, the confirmation of parallel calculation technology, the conceptual design of platform, the development of demonstration program of platform are performed. Based upon studies stated above, the VES development plan including prototype development during the period of selection of the site candidate was studied. The concept of VES was build based on the examination stated above. (author)

Conceptual design of the Virtual Engineering System for High Level Radioactive Waste Geological Disposal

International Nuclear Information System (INIS)

1999-06-01

The Virtual Engineering System for the High Level Radioactive Waste Geological Disposal (hereafter the VE) adopts such computer science technologies as advanced numerical simulation technology with special emphasis upon computer graphics, massive parallel computing, high speed networking, knowledge engineering, database technology to virtually construct the natural and the part of social environment of disposal site in syberspace to realize the disposal OS as its final target. The principle of tile VE is to provide for a firm business standpoint after The 2000 Report by JNC and supply decision support system which promotes various evaluations needed to be done from the year of 2000 to the licensing application for disposal to the government. The VE conceptual design was performed in the year of 1998. The functions of the VE are derived from the analysis of work scope of implementing organization in each step of geological waste disposal: the VE functions need the safety performance assessment, individual process analysis, facility designing, cost evaluation, site surveillance, research and development, public acceptance. Then the above functions are materialized by integrating such individual system as geology database, groundwater database, safety performance assessment system, coupled phenomena analysis system, decision support system, cost evaluation system, and public acceptance system. The integration method of the systems was studied. The concept of the integration of simulators has also been studied from the view point of CAPASA program. Parallel computing, networking, and computer graphic for high speed massive scientific calculation were studied in detail as the element technology to achieve the VE. Based on studies stated above, the concept of the waste disposal project and subjects that arise from 1999 to licensing application are decided. (author)

Geological disposal of high level radioactive waste in China: progress during 1985-2004

International Nuclear Information System (INIS)

Wang Ju; Xu Guoqing; Zheng Hualing; Fan Xianhua; Wang Chengzu; Fan Zhiwen

2005-01-01

Safe disposal of high level radioactive waste (HLW) is a challenging issue for the sustainable development of nuclear energy. The studies for the disposal of HLW in China started in 1985, the proposed goal was to build China's high level waste repository by mid-21st Century, while the waste to be disposed of will be vitrified waste, transuranic waste and small amount of spent fuel. The proposed repository was a shaft-tunnel-silo model hosted by granite in saturated zone. In the period of 1985 to 2004, progress was made in China's HLW disposal program. It was decided that 'deep geological disposal' will be used to dispose of China's HLW, while the technical strategy for the development of repository will a 3-step strategy, that includes steps of site selection and site evaluation, construction of underground research laboratory, and construction of repository. Based on nation wide screening, the Beishan area, Gansu Province, northwestern China, located in Gobi desert area with few inhabitants, integral crust structure and favorable geological and hydrogeological conditions, was selected as the most potential area for China's repository. In early 1990's, site selection for underground research laboratory was conducted, 2 sites in the suburb of Beijing were preliminarily selected as the potential sites for a 'generic underground research laboratory'. It was determined to use bentonite as backfill material for the repository, while the bentonite from Gaomiaozi deposit in Inner Mongolia was selected as potential buffer and backfill material for China's repository. The studies on the mineralogical, geotechnical, physico-mechanical and thermal properties of the Gaomiaozi bentonite have been conducting. Some parameters such as sorption radio, diffusion coefficient and dispersion coefficient of radionuclides (Np, Pu and Tc) in Beishan granite and bentonite have been obtained. A low-oxygen glove box and a device simulating the temperature, pressure and redox potential of

Biosphere modeling for safety assessment to high-level radioactive waste geological disposal. Application of reference biosphere methodology to safety assesment of geological disposal

International Nuclear Information System (INIS)

Baba, Tomoko; Ishihara, Yoshinao; Ishiguro, Katsuhiko; Suzuki, Yuji; Naito, Morimasa

2000-01-01

In the safety assessment of a high-level radioactive waste disposal system, it is required to estimate future radiological impacts on human beings. Consideration of living habits and the human environment in the future involves a large degree of uncertainty. To avoid endless speculation aimed at reducing such uncertainty, an approach is applied for identifying and justifying a 'reference biosphere' for use in safety assessment in Japan. considering a wide range of Japanese geological environments, saline specific reference biospheres' were developed using an approach consistent with the BIOMOVS II reference biosphere methodology. (author)

Disposal of high-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Costello, J M [Australian Atomic Energy Commission Research Establishment, Lucas Heights

1982-03-01

The aims and options for the management and disposal of highly radioactive wastes contained in spent fuel from the generation of nuclear power are outlined. The status of developments in reprocessing, waste solidification and geologic burial in major countries is reviewed. Some generic assessments of the potential radiological impacts from geologic repositories are discussed, and a perspective is suggested on risks from radiation.

A preliminary study on the regional fracture systems for deep geological disposal of high level radioactive waste in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Chun Soo; Bae, Dae Seok; Kim, Kyung Su; Koh, Young Kown; Park, Byoung Yoon [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-03-01

For the deep geological disposal of high-level radioactive waste, it is essential to characterize the fracture system in rock mass which has a potential pathways of nuclide. Currently, none of research results are in classification and detailed properties for the fracture system in Korea. This study aims to classify and describe the regional fracture system in lithological and geotectonical point of view using literature review, shaded relief map, and aeromagnetic survey data. This report contains the following: - Theoretical review of the fracture development mechanism. - Overall fault and fracture map. - Geological description on the distributional characteristics of faults and fractures(zone) in terms of lithological domain and tectonical province. 122 refs., 22 figs., 4 tabs. (Author)

Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada

International Nuclear Information System (INIS)

1999-01-01

The Proposed Action addressed in this EIS is to construct, operate and monitor, and eventually close a geologic repository at Yucca Mountain in southern Nevada for the disposal of spent nuclear fuel and high-level radioactive waste currently in storage at 72 commercial and 5 DOE sites across the United States. The EIS evaluates (1) projected impacts on the Yucca Mountain environment of the construction, operation and monitoring, and eventual closure of the geologic repository; (2) the potential long-term impacts of repository disposal of spent nuclear fuel and high-level radioactive waste; (3) the potential impacts of transporting these materials nationally and in the State of Nevada; and (4) the potential impacts of not proceeding with the Proposed Action

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

Cotton, T.

1985-01-01

With the passage of the Nuclear Waste Policy Act of 1982 (NWPA), Congress for the first time established in law a comprehensive Federal policy for commercial high-level radioactive waste management, including interim storage and permanent disposal. NWPA provides sufficient authority for developing and operating a high-level radioactive waste management system based on disposal in mined geologic repositories. Authorization for other types of waste facilities will not be required unless major problems with geologic disposal are discovered, and studies to date have identified no insurmountable technical obstacles to developing geologic repositories. The NWPA requires the Department of Energy (DOE) to submit to Congress three key documents: (1) a Mission Plan, containing both a waste management plan with a schedule for transferring waste to Federal facilities and an implementation program for choosing sites and developing technologies to carry out that plan; (2) a monitored retrievable storage (MRS) proposal, to include a site-specific design for a long-term federal storage facility, an evaluation of whether such an MRS facility is needed and feasible, and an analysis of how an MRS facility would be integrated with the repository program if authorized by Congress; and (3) a study of alternative institutional mechanisms for financing and managing the radioactive waste system, including the option of establishing an independent waste management organization outside of DOE. The Mission Plan and the report on alternative institutional mechanisms were submitted to the 99th US Congress in 1985. The MRS proposal is to be submitted in early 1986. Each of these documents is discussed following an overview of the Nuclear Waste Policy Act of 1982

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 2. Engineering technology for geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the deep geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, part 2 of the progress report, concerns engineering aspect with reference to Japanese geological disposal plan, according to which the vitrified HLW will be disposed of into a deep, stable rock mass with thick containers and surrounding buffer materials at the depth of several hundred meters. It discusses on multi-barrier systems consisting of a series of engineered and natural barriers that will isolate radioactive nuclides effectively and retard their migrations to the biosphere environment. Performance of repository components, including specifications of containers for vitrified HLW and their overpacks under design as well as buffer material such as Japanese bentonite to be placed in between are described referring also to such possible problems as corrosion arising from the supposed system. It also presents plans and designs for underground disposal facilities, and the presumed management of the underground facilities. (Ohno, S.)

Geological and geotechnical limitations of radioactive waste retrievability in geologic disposals

Energy Technology Data Exchange (ETDEWEB)

Stahlmann, Joachim; Leon-Vargas, Rocio; Mintzlaff, Volker; Treidler, Ann-Kathrin [TU Braunschweig (Germany). Inst. for Soil Mechanics and Foundation Engineering

2015-07-01

The capability of retrieving radioactive waste emplaced in deep geological formations is nowadays in discussion in many countries. Based on the storage of high-level radioactive waste (HAW) in deep geological repositories there is a number of possible scenarios for their retrieval. Measurements for an improved retrieving capability may impact on the geotechnical and geological barriers, e.g. keeping open the access drifts for a long period of time can result in a bigger evacuation damage zone (EDZ) in the host rock which implies potential flow paths for ground water. Nevertheless, to limit the possible scenarios associated to the retrieval implementation, it is necessary to take in consideration which criteria will be used for an efficient monitoring program, while clearly determining the performance reliability of the geotechnical barriers. In addition, the integrity of the host rock as geological barrier has to be verified. Therefore, it is important to evaluate different design solutions and the most appropriate measurement methods to improve the retrievability process of wastes from a geological repository. A short presentation of the host rocks is given is this paper.

Does geology help in the final disposal of radioactive wastes?

International Nuclear Information System (INIS)

Schaer, U.

1987-01-01

High-level radioactive wastes have to be stored safely for thousands of years in deep geological formations. The question discussed is whether or not a geological prognosis over this span of time is possible. The main problem is groundwater

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

1985-03-01

This report presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste. It is intended to contribute to the implementation of Nuclear Waste Policy Act of 1982 (NWPA). The major conclusion of that review is that NWPA provides sufficient authority for developing and operating a waste management system based on disposal in geologic repositories. Substantial new authority for other facilities will not be required unless major unexpected problems with geologic disposal are encountered. OTA also concludes that DOE's Draft Mission Plan published in 1984 falls short of its potential for enhancing the credibility and acceptability of the waste management program

The JAERI program for development of safety assessment models and acquisition of data needed for assessment of geological disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Matsuzuru, H.

1991-01-01

The JAERI is conducting R and D program for the development of safety assessment methodologies and the acquisition of data needed for the assessment of geologic disposal of high-level radioactive wastes, aiming at the elucidation of feasibility of geologic disposal in Japan. The paper describes current R and D activities to develop interim versions of both a deterministic and a probabilistic methodologies based on a normal evolution scenario, to collect data concerning engineered barriers and geologic media through field and laboratory experiments, and to validate the models used in the methodologies. 2 figs., 2 refs

Proposal for basic safety requirements regarding the disposal of high-level radioactive waste

International Nuclear Information System (INIS)

1980-04-01

A working group commissioned to prepare proposals for basic safety requirements for the storage and transport of radioactive waste prepared its report to the Danish Agency of Environmental Protection. The proposals include: radiation protection requirements, requirements concerning the properties of high-level waste units, the geological conditions of the waste disposal location, the supervision of waste disposal areas. The proposed primary requirements for safety evaluation of the disposal of high-level waste in deep geological formations are of a general nature, not being tied to specific assumptions regarding the waste itself, the geological and other conditions at the place of disposal, and the technical methods of disposal. It was impossible to test the proposals for requirements on a working repository. As no country has, to the knowledge of the working group, actually disposed of hifg-level radioactive waste or approved of plans for such disposal. Methods for evaluating the suitability of geological formations for waste disposal, and background material concerning the preparation of these proposals for basic safety requirements relating to radiation, waste handling and geological conditions are reviewed. Appended to the report is a description of the phases of the fuel cycle that are related to the storage of spent fuel and the disposal of high-level reprocessing waste in a salt formation. It should be noted that the proposals of the working group are not limited to the disposal of reprocessed fuel, but also include the direct disposal of spent fuel as well as disposal in geological formations other than salt. (EG)

Geo-metadata design for the GIS of the pre-selected site for China's high-level radioactive waste repository

International Nuclear Information System (INIS)

Zhong Xia; Wang Ju; Huang Shutao; Wang Shuhong; Gao Min

2008-01-01

The information system for the geological disposal of high-level radioactive waste aims at the integrated management and full application of multi-sourceful information in the research for geological disposal of high-level radioactive waste. And the establishment and operation of the system need geo-metadata's support of multi-sourceful information. In the paper, on the basis of geo-data analysis for pre-selected site of disposal of high-level radioactive waste, we can apply the existing metadata standards. Also we can research and design the content information, management pattern and application for geo-metadata of the multi-sourceful information. (authors)

Low-level radioactive waste program of the US Geological Survey - in transition

International Nuclear Information System (INIS)

Fischer, J.N.

1983-01-01

In 1983, the US Geological Survey will publish final reports of geohydrologic investigations at five commercial low-level, radioactive-waste burial sites in the United States. These reports mark the end of the first phase of the US Geological Survey program to improve the understanding of earth-science principles related to the effective disposal of low-level wastes. The second phase, which was initiated in 1981, is being developed to address geohydrologic issues identified as needing greater attention based upon results of the first-phase site studies. Specific program elements include unsaturated-zone hydrology, geochemistry, clay mineralogy, surface geophysical techniques, and model development and testing. The information and expertise developed from these and previous studies will allow the US Geological Survey to provide sound technical assistance to State low-level waste compacts, the Department of Energy, the Nuclear Regulatory Commission, and the Environmental Protection Agency. 11 references

Geological problems in radioactive waste isolation

International Nuclear Information System (INIS)

Witherspoon, P.A.

1991-01-01

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, ''Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately

Geological problems in radioactive waste isolation

Energy Technology Data Exchange (ETDEWEB)

Witherspoon, P.A. (ed.)

1991-01-01

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

Discussion of quantitative assessment index system of suitability of the site for geological disposal repository of high-level radioactive waste

International Nuclear Information System (INIS)

Su Rui; Wang Ju

2014-01-01

Site selection and suitability assessment of site are one of important tasks of research and development of geological disposal engineering for high-level radioactive waste (HLW). Quantitative assessment of suitability of the site is based on the scientific, reasonable and operational index system. The discussion of index screening of quantitative assessment of suitability of the site is conducted. Principle of index screening is presented and index systems are established for different stages of site selection, including planning stage of site selection, region or area investigation stage, site characterization and site confirmation stage. But the considerations are taken of the complexity of site selection of geological disposal engineering for HLW and itself development of quantitative assessment method, so improvement of the index systems presented above is needed in the further. (authors)

Review on influences of colloids on geologic disposal of high level radioactive waste. For better understanding of natural colloidal materials

International Nuclear Information System (INIS)

Kanai, Yutaka; Suzuki, Masaya; Kamioka, Hikari; Yoshida, Takahiro; Suko, Takeshi

2007-01-01

Although the influences of colloidal materials on radionuclide transport in geological media are pointed out, their behaviors in natural environment have not yet been well elucidated and therefore their influences on the geologic disposal of high-level radioactive waste (HLW) are not fully estimated quantitatively. This paper reviewed the studies on natural colloids, especially focused on inorganic, organic and biological colloids, and discussed the future works to be carried out. Much attention should be paid to the sampling and analysis. Excellent techniques for in-situ observation, concentration without changing the state of colloid, standard procedure for analysis, are necessary to be developed. More research studies on the behaviors of colloids are required in not only far- and near-fields but also items on effects of the environments and its evolution. (author)

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Introductory part and summaries

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan and comprises seven chapters. Chapter I briefly describes the importance of HLW management in promoting nuclear energy utilization. According to the long-term program, the HLW separated from spent fuels at reprocessing plants is to be vitrified and stored for a period of 30 to 50 years to allow cooling, then be disposed of in a deep geological formation. Chapter II mainly explains the concepts of geological disposal in Japan. Chapters III to V are devoted to discussions on three important technical elements (the geological environment of Japan, engineering technology and safety assessment of the geological disposal system) which are necessary for reliable realization of the geological disposal concept. Chapter VI demonstrates the technical ground for site selection and for setup of safety standards of the disposal. Chapter VII summarizes together with plans for future research and development. (Ohno, S.)

Selection and Basic Properties of the Buffer Material for High-Level Radioactive Waste Repository in China

Institute of Scientific and Technical Information of China (English)

WEN Zhijian

2008-01-01

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

Studies on site characterization methodologies for high level radioactive waste disposal

International Nuclear Information System (INIS)

Wang Ju; Guo Yonghai; Chen Weiming

2008-01-01

This paper presents the final achievement of the project 'Studies of Site-specific Geological Environment for High Level Waste Disposal and Performance Assessment Methodology, Part Ⅰ: Studies on Site Characterization Methodologies for High Level Radioactive Waste Disposal', which is a 'Key Scientific and Technological Pre-Research Project for National Defense' during 2001-2005. The study area is Beishan area, Gansu Province, NW China--the most potential site for China's underground research laboratory and high level radioactive waste repository. The boreholes BS01, BS2, BS03 and BS04 drilled in fractured granite media in Beishan are used to conduct comprehensive studies on site characterization methodologies, including: bore hole drilling method, in situ measurement methods of hydrogeological parameters, underground water sampling technology, hydrogeochemical logging method, geo-stress measurement method, acoustic borehole televiewer measurement method, borehole radar measurement method, fault stability evaluation methods and rock joint evaluation method. The execution of the project has resulted in the establishment of an 'Integrated Methodological System for Site Characterization in Granite Site for High Level Radioactive Waste Repository' and the 8 key methodologies for site characterization: bore hole drilling method with minimum disturbance to rock mass, measurement method for hydrogeological parameters of fracture granite mass, in situ groundwater sampling methods from bore holes in fractured granite mass, fracture measurement methods by borehole televiewer and bore radar system, hydrogeochemical logging, low permeability measurement methods, geophysical methods for rock mass evaluation, modeling methods for rock joints. Those methods are comprehensive, advanced, innovative, practical, reliable and of high accuracy. The comprehensive utilization of those methods in granite mass will help to obtain systematic parameters of

Management of commercial high-level and transuranium-contaminated radioactive wastes. Environmental statement

International Nuclear Information System (INIS)

1974-09-01

This Draft Environmental Statement is issued to assess the environmental impact of the AEC's program to manage commercial high-level and transuranium-contaminated radioactive wastes. These are the types of commercial radioactive wastes for which AEC custody is required by present or anticipated regulations. The program consists of three basic parts: development of a Retrievable Surface Storage Facility (RSSF) for commercial high-level waste, using existing technology; evaluating geological formations and sites for the development of a Geological Disposal Pilot Plant (GDPP) which would lead to permanent disposal; and providing retrievable storage for the transuranium-contaminated waste pending availability of permanent disposal. Consideration has been given to all environmental aspects of the program, using waste generation projections through the year 2000. Radiological and other impacts of implementing the program are expected to be minimal, but will be discussed in further environmental statements which will support budget actions for specific repositories. The alternatives discussed in this Draft Environmental Statement are presented. (U.S.)

On area-specific underground research laboratory for geological disposal of high-level radioactive waste in China

Directory of Open Access Journals (Sweden)

Ju Wang

2014-04-01

Full Text Available Underground research laboratories (URLs, including “generic URLs” and “site-specific URLs”, are underground facilities in which characterisation, testing, technology development, and/or demonstration activities are carried out in support of the development of geological repositories for high-level radioactive waste (HLW disposal. In addition to the generic URL and site-specific URL, a concept of “area-specific URL”, or the third type of URL, is proposed in this paper. It is referred to as the facility that is built at a site within an area that is considered as a potential area for HLW repository or built at a place near the future repository site, and may be regarded as a precursor to the development of a repository at the site. It acts as a “generic URL”, but also acts as a “site-specific URL” to some extent. Considering the current situation in China, the most suitable option is to build an “area-specific URL” in Beishan area, the first priority region for China's high-level waste repository. With this strategy, the goal to build China's URL by 2020 may be achieved, but the time left is limited.

Elementary migration around the Oklo nuclear reactors. Implications for high level radioactive wastes storage

International Nuclear Information System (INIS)

Menet-Dressayre, C.; Menager, M.T.

1993-01-01

The study of Uranium and rare earths near the reactors has displayed the radioelements transfer in the reactors neighbourhood. The main implications for high level radioactive wastes disposal in geological formations are discussed. 12 refs

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

Importance of geologic characterization of potential low-level radioactive waste disposal sites

Science.gov (United States)

Weibel, C.P.; Berg, R.C.

1991-01-01

Using the example of the Geff Alternative Site in Wayne County, Illinois, for the disposal of low-level radioactive waste, this paper demonstrates, from a policy and public opinion perspective, the importance of accurately determining site stratigraphy. Complete and accurate characterization of geologic materials and determination of site stratigraphy at potential low-level waste disposal sites provides the frame-work for subsequent hydrologic and geochemical investigations. Proper geologic characterization is critical to determine the long-term site stability and the extent of interactions of groundwater between the site and its surroundings. Failure to adequately characterize site stratigraphy can lead to the incorrect evaluation of the geology of a site, which in turn may result in a lack of public confidence. A potential problem of lack of public confidence was alleviated as a result of the resolution and proper definition of the Geff Alternative Site stratigraphy. The integrity of the investigation was not questioned and public perception was not compromised. ?? 1991 Springer-Verlag New York Inc.

Preliminary assessment of the radiological protection aspects of disposal of high-level waste in geologic formations

International Nuclear Information System (INIS)

Hill, M.D; Grimwood, P.D.

1978-01-01

The purpose of this study is to carry out a preliminary assessment of the potential radiological consequences of disposing of vitrified high-level radioactive waste in geologic formations. The events which could lead to the release of radioactivity from a geologic repository are reviewed and ingress of ground-water is identified as the principal mechanism by which radioactivity may be transported back to the biosphere. A mathematical model of radionuclide migration with ground-water is used to predict possible rates of release of radioactivity into fresh water from a hypothetical repository containing all the high-level waste which may be generated in the UK up to the year 2000. The individual and collective doses which could be received as a result of man's use of contaminated fresh water are evaluated. The numerical results of the study depend very much on the assumptions made and cannot be used to draw any detailed conclusions. The main result is the identification of areas where further studies are required in order to carry out a full evaluation of this disposal option. (author)

Planning and Design Considerations for Geological Repository Programmes of Radioactive Waste

International Nuclear Information System (INIS)

2014-11-01

Disposal in a geological repository is the generally accepted solution for the long term management of high level and/or long lived radioactive wastes, in line with the general principles defined in the IAEA Safety Fundamentals. This publication presents practical information on the way a geological repository programme for radioactive waste could be defined and planned, with special attention to all aspects having an impact on the timing. Country specific examples for repository development phases are provided, based on actual experiences from Member States

Geological repository layout for radioactive high level long lived waste in argillite

International Nuclear Information System (INIS)

Gaussen, JL

2006-01-01

In the framework of the 1991 French radioactive waste act, ANDRA has studied the feasibility of a geological repository in the argillite layer of the Bure site for high level long lived waste. This presentation is focussed on the underground facilities which constitute the specific component of this project. The preliminary underground layout which has been elaborated is based on four categories of data: - the waste characteristics and inventory; - the geological properties of the host argillite; - the long term performance objectives of the repository; - the specifications in terms of operation and reversibility. The underground facilities consist of two types of works: the access works (shafts and drifts) and the disposal cells. The function of the access works is to permit the implementation of two concurrent activities: the nuclear operations (transfer and emplacement of the disposal packages into the disposal cells) and the construction of the next disposal cells. The design of the drifts network which matches up to this function is also influenced by two other specifications: the minimization of the drift dimensions in order to limit their influence on the integrity of the geological formation and the necessity of a safe ventilation in case of fire. The resulting layout is a network of 4 parallel drifts (2 of them being dedicated to the operation, the other two being dedicated to the construction activities). The average diameter of these access drifts is 7 meters. The link between the surface and the underground is ensured by 4 shafts. The most important function of the disposal cells is to contribute to the long term performance of the repository. In this regard, the thermal and geotechnical considerations play an important role. The B wastes (intermediate level wastes) are not (or not very) exothermic. Consequently, the design of their disposal cells result mainly from geotechnical considerations. The disposal packages (made of concrete) are piled up in

Methods of Disposing Of High-Level Radioactive Waste: A Review

International Nuclear Information System (INIS)

Abumurade, K.

2002-01-01

High level nuclear waste from both commercial reactors and defense industry presents a difficult problem to the scientific community as well as the public. The solutions to this problem is still debatable both technically and ethically. There are few methods proposed for disposing of high level waste. Each method has its own advantages and disadvantages. However, the very deep underground geologic repository is the best choice for disposing of high-level radioactive wastes. The cost benefit equation of nuclear power production and its waste is discussed. However, the public should be educated about this matter to minimize the gap between them and the nuclear power community including scientists industry, and governments. (Author) 15 refs., 4 tabs., 1 fig

Geological problems in radioactive waste isolation - second worldwide review

International Nuclear Information System (INIS)

Witherspoon, P.A.

1996-09-01

The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19, 1989 in Washington, D.C. Reports from 15 countries were presented at the workshop and four countries provided reports after the workshop, so that material from 19 different countries was included in the first review. It was apparent from the widespread interest in this first review that the problem of providing a permanent and reliable method of isolating radioactive waste from the biosphere is a topic of great concern among the more advanced, as well as the developing, nations of the world. This is especially the case in connection with high-level waste (HLW) after its removal from nuclear power plants. The general concensus is that an adequate isolation can be accomplished by selecting an appropriate geologic setting and carefully designing the underground system with its engineered barriers. This document contains the Second Worldwide Review of Geological Problems in Radioactive Waste Isolation, dated September 1996

Geological problems in radioactive waste isolation - second worldwide review

Energy Technology Data Exchange (ETDEWEB)

Witherspoon, P.A. [ed.

1996-09-01

The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19, 1989 in Washington, D.C. Reports from 15 countries were presented at the workshop and four countries provided reports after the workshop, so that material from 19 different countries was included in the first review. It was apparent from the widespread interest in this first review that the problem of providing a permanent and reliable method of isolating radioactive waste from the biosphere is a topic of great concern among the more advanced, as well as the developing, nations of the world. This is especially the case in connection with high-level waste (HLW) after its removal from nuclear power plants. The general concensus is that an adequate isolation can be accomplished by selecting an appropriate geologic setting and carefully designing the underground system with its engineered barriers. This document contains the Second Worldwide Review of Geological Problems in Radioactive Waste Isolation, dated September 1996.

Geological aspects of radioactive waste disposal

International Nuclear Information System (INIS)

Kobera, P.

1985-01-01

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

The management of high-level radioactive wastes

International Nuclear Information System (INIS)

Lennemann, Wm.L.

1979-01-01

The definition of high-level radioactive wastes is given. The following aspects of high-level radioactive wastes' management are discussed: fuel reprocessing and high-level waste; storage of high-level liquid waste; solidification of high-level waste; interim storage of solidified high-level waste; disposal of high-level waste; disposal of irradiated fuel elements as a waste

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)

Geological disposal of high-level radioactive waste and the role of rock engineering

International Nuclear Information System (INIS)

Sugihara, Kozo

2008-01-01

Japan Atomic Energy Agency (JAEA) and its predecessors have been conducting an extensive geoscientific research program since the 1970's in order to contribute to the formation of a firm scientific and technological basis for the geological disposal of high level radioactive waste in Japan. As a part of this program, in situ experiments have been performed at the Tono Mine in soft sedimentary rocks and at the Kamaishi Mine in hard crystalline rocks. An experiment on excavation disturbance has been one of these experiments and has revealed the extent and properties of the excavation disturbed zone (EDZ) and the applicability of available measurement methods. It is suggested that mechanical excavation and controlled excavation have reduced excavation damage of the rock mass around a drift, although some improvements in the currently available methods for measuring and simulating the EDZ are essential to understand excavation disturbance in more detail. JAEA is now promoting two underground research laboratory projects in Japan; the Mizunami Underground Research Laboratory (MIU) project for crystalline rocks and the Horonobe Underground Research Laboratory (Horonobe URL) project for sedimentary rocks. From a rock mechanical point of view, the major interest in these projects will be paid to failure phenomenon deep underground, rock stress estimation at larger scales and long-term physical stability of underground structure. These projects are open for international collaboration. (author)

A preliminary study on the geochemical environment for deep geological disposal of high level radioactive waste in Korea

International Nuclear Information System (INIS)

Kim, Chun Soo; Bae, Dae Seok; Kim, Kyung Su; Koh, Yong Kwon; Park, Byoung Yun

2000-03-01

Geochemical study on the groundwater from crystalline rocks (granite and gneiss) for the deep geological disposal of high-level radioactive waste was carried out in order to elucidate the hydrogeochemical and isotope characteristics and geochemical evolution of the groundwater. Study areas are Jungwon, Chojeong, Youngcheon and Yusung for granite region, Cheongyang for gneiss region, and Yeosu for volcanic region. Groundwaters of each study areas weree sampled and analysed systematically. Groundwaters can be grouped by their chemistry and host rock. Origin of the groundwater was proposed by isotope ( 18 O, 2 H, 13 C, 34 S, 87 Sr, 15 N) studies and the age of groundwater was inferred from their tritium contents. Based ont the geochemical and isotope characteristics, the geochemical evolutions of each types of groundwater were simulated using SOLVEQ/CHILLER and PHREEQC programs

2005 dossier. ANDRA's researches on the geological disposal of high-level and long-lived radioactive wastes. Results and perspectives

International Nuclear Information System (INIS)

2005-06-01

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 deep geologic formations (argilites and granites). Content: 1 - Research on deep disposal of radioactive waste: general interest task: Legislative framework, ANDRA scientific objectives, Inspections and assessments; 2 - Designing a safe and reversible disposal system: Repository safety, Reversibility: an essential requirement; 3 - Clay Research on a repository in a clay formation, A long research programme, Dossier 2005 Argile; 4 - Meuse/Haute-Marne site clay: Expected properties of the rock formation, Choice of argillite, Meuse/Haute-Marne site, Conclusions from 10 years of research at the Meuse/Haute-Marne site; 5 - Repository installations: Safe and reversible architecture, Disposal of B waste, Disposal of C waste, Possible disposal of spent fuel (CU); 6 - The disposal facility in operation: From waste packages reception to their disposal in cells, Stages of the progressive closure of engineered structures; 7 - Reversible management: Freedom of choice for future generations, Various closure stages; 8 - Long-term evolution of the repository: Apprehending the repository complexity Main evolutions expected, Slow and limited release of radioactive substances; 9 - Repository safety and impact on man: Several evolution scenarios, Normal evolution, Altered evolution; 10 - Granite Research on a repository in a granite formation: A global approach, Scientific co-operations, Dossier 2005 Granite; 11 - Characteristics of French granite formations: What properties are required for a repository?, Different types of granite formations; 12 - Repository installations: Repository design adapted to granite fractures, Clay seals to prevent water flows, Waste disposal packages ensuring long-term leak-tightness, Physical and chemical environment favourable for waste packages, Architecture

Site selection factors for repositories of solid high-level and alpha-bearing wastes in geological formations

International Nuclear Information System (INIS)

1977-01-01

The purpose of this report is to provide guidelines for the selection and evaluation of suitable areas and sites for the disposal of solid high-level and alpha-bearing wastes into geological formations. This report is also intended to provide summary information on many types of geological formations underlying the land masses that might be considered as well as guidance on the geological and hydrological factors that should be investigated to demonstrate the suitability of the formations. In addition, other factors that should be considered in selecting a site for a radioactive waste repository are discussed briefly. The information, as presented, was developed to the extent of current technology for application to the evaluation of deep (greater than about 300 metres below ground level) geological formations in the selection of suitable areas for the disposal of solid or solidified high-level and alpha-bearing wastes. The extreme complexity of many geological environments and of the rock features that govern the presence and circulation of groundwater does not make it feasible to derive strict criteria for the selection of a site for a radioactive waste repository in a geological formation. Each potential repository location must be evaluated according to its own unique geological and hydrological setting. Therefore, only general guidance is offered, and this is done through discussion of the many factors that need to be considered in order to obtain the necessary assurances that the radionuclides will be confined in the geological repository over the required period of time

Site selection factors for repositories of solid high-level and alpha-bearing wastes in geological formations

Energy Technology Data Exchange (ETDEWEB)

1977-01-01

The purpose of this report is to provide guidelines for the selection and evaluation of suitable areas and sites for the disposal of solid high-level and alpha-bearing wastes into geological formations. This report is also intended to provide summary information on many types of geological formations underlying the land masses that might be considered as well as guidance on the geological and hydrological factors that should be investigated to demonstrate the suitability of the formations. In addition, other factors that should be considered in selecting a site for a radioactive waste repository are discussed briefly. The information, as presented, was developed to the extent of current technology for application to the evaluation of deep (greater than about 300 meters below ground level) geological formations in the selection of suitable areas for the disposal of solid or solidified high-level and alpha-bearing wastes. The extreme complexity of many geological environments and of the rock features that govern the presence and circulation of groundwater does not make it feasible to derive strict criteria for the selection of a site for a radioactive waste repository in a geological formation. Each potential repository location must be evaluated according to its own unique geological and hydrological setting. Therefore, only general guidance is offered, and this is done through discussion of the many factors that need to be considered in order to obtain the necessary assurances that the radionuclides will be confined in the geological repository over the required period of time.

Recovering method for high level radioactive material

International Nuclear Information System (INIS)

Fukui, Toshiki

1998-01-01

Offgas filters such as of nuclear fuel reprocessing facilities and waste control facilities are burnt, and the burnt ash is melted by heating, and then the molten ashes are brought into contact with a molten metal having a low boiling point to transfer the high level radioactive materials in the molten ash to the molten metal. Then, only the molten metal is evaporated and solidified by drying, and residual high level radioactive materials are recovered. According to this method, the high level radioactive materials in the molten ashes are transferred to the molten metal and separated by the difference of the distribution rate of the molten ash and the molten metal. Subsequently, the molten metal to which the high level radioactive materials are transferred is heated to a temperature higher than the boiling point so that only the molten metal is evaporated and dried to be removed, and residual high level radioactive materials are recovered easily. On the other hand, the molten ash from which the high level radioactive material is removed can be discarded as ordinary industrial wastes as they are. (T.M.)

High Level Radioactive Waste Management

International Nuclear Information System (INIS)

1991-01-01

The proceedings of the second annual international conference on High Level Radioactive Waste Management, held on April 28--May 3, 1991, Las Vegas, Nevada, provides information on the current technical issue related to international high level radioactive waste management activities and how they relate to society as a whole. Besides discussing such technical topics as the best form of the waste, the integrity of storage containers, design and construction of a repository, the broader social aspects of these issues are explored in papers on such subjects as conformance to regulations, transportation safety, and public education. By providing this wider perspective of high level radioactive waste management, it becomes apparent that the various disciplines involved in this field are interrelated and that they should work to integrate their waste management activities. Individual records are processed separately for the data bases

Geology of high-level nuclear waste disposal: an introduction

International Nuclear Information System (INIS)

Roxbugh, I.S.

1987-01-01

Hazardous waste is produced by the nuclear fuel cycle from mining and milling of uranium ore, refinement and enrichment, reactor use, and during reprocessing of spent fuel. Waste can be classified according to origin, physical state, and levels of radioactivity and radiotoxicity. The method of the long-term waste disposal is based on the degree of the hazard and the length of time (1000 years to millions of years) for the waste to become safe. The International Atomic Energy Agency (IAEA) has classified radioactive waste into five categories (I-V) based on the amount of radioactivity and heat output of the waste. The text is concerned mainly with the two most hazardous categories (I and II). Disposal at various geological sites using proven mining, engineering, and deep drilling techniques has been proposed and studied. An ideal geological repository would have (1) minimum ground water movement, (2) geochemical and mineralogical properties to retard or immobilize the effects of the nuclear waste from reaching the biosphere, (3) thermochemical properties to allow for heat loading without damage, and (4) structural strength for the operational period. Types of geological environments (both undersea and on land) include evaporites, crystalline rocks, and argillaceous deposits. European and North American case histories are described, and there is a glossary and an extensive list of references in this concise review

Geology of the Yucca Mountain Region, Chapter in Stuckless, J.S., ED., Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste

International Nuclear Information System (INIS)

J.S. Stuckless; D. O'Leary

2006-01-01

Yucca Mountain has been proposed as the site for the Nation's first geologic repository for high-level radioactive waste. This chapter provides the geologic framework for the Yucca Mountain region. The regional geologic units range in age from late Precambrian through Holocene, and these are described briefly. Yucca Mountain is composed dominantly of pyroclastic units that range in age from 11.4 to 15.2 Ma. The proposed repository would be constructed within the Topopah Spring Tuff, which is the lower of two major zoned and welded ash-flow tuffs within the Paintbrush Group. The two welded tuffs are separated by the partly to nonwelded Pah Canyon Tuff and Yucca Mountain Tuff, which together figure prominently in the hydrology of the unsaturated zone. The Quaternary deposits are primarily alluvial sediments with minor basaltic cinder cones and flows. Both have been studied extensively because of their importance in predicting the long-term performance of the proposed repository. Basaltic volcanism began about 10 Ma and continued as recently as about 80 ka with the eruption of cones and flows at Lathrop Wells, approximately 10 km south-southwest of Yucca Mountain. Geologic structure in the Yucca Mountain region is complex. During the latest Paleozoic and Mesozoic, strong compressional forces caused tight folding and thrust faulting. The present regional setting is one of extension, and normal faulting has been active from the Miocene through to the present. There are three major local tectonic domains: (1) Basin and Range, (2) Walker Lane, and (3) Inyo-Mono. Each domain has an effect on the stability of Yucca Mountain

The Beishan underground research laboratory for geological disposal of high-level radioactive waste in China: Planning, site selection, site characterization and in situ tests

Directory of Open Access Journals (Sweden)

Ju Wang

2018-06-01

Full Text Available With the rapid development of nuclear power in China, the disposal of high-level radioactive waste (HLW has become an important issue for nuclear safety and environmental protection. Deep geological disposal is internationally accepted as a feasible and safe way to dispose of HLW, and underground research laboratories (URLs play an important and multi-faceted role in the development of HLW repositories. This paper introduces the overall planning and the latest progress for China's URL. On the basis of the proposed strategy to build an area-specific URL in combination with a comprehensive evaluation of the site selection results obtained during the last 33 years, the Xinchang site in the Beishan area, located in Gansu Province of northwestern China, has been selected as the final site for China's first URL built in granite. In the process of characterizing the Xinchang URL site, a series of investigations, including borehole drilling, geological mapping, geophysical surveying, hydraulic testing and in situ stress measurements, has been conducted. The investigation results indicate that the geological, hydrogeological, engineering geological and geochemical conditions of the Xinchang site are very suitable for URL construction. Meanwhile, to validate and develop construction technologies for the Beishan URL, the Beishan exploration tunnel (BET, which is a 50-m-deep facility in the Jiujing sub-area, has been constructed and several in situ tests, such as drill-and-blast tests, characterization of the excavation damaged zone (EDZ, and long-term deformation monitoring of surrounding rocks, have been performed in the BET. The methodologies and technologies established in the BET will serve for URL construction. According to the achievements of the characterization of the URL site, a preliminary design of the URL with a maximum depth of 560 m is proposed and necessary in situ tests in the URL are planned. Keywords: Beishan, Xinchang site, Granite

Hydrologic and geologic aspects of low-level radioactive-waste site management

International Nuclear Information System (INIS)

Cutshall, N.H.; Vaughan, N.D.; Haase, C.S.; Olsen, C.R.; Huff, D.D.

1982-01-01

Hydrologic and geologic site characterization is a critical phase in development of shallow land-burial sites for low-level radioactive-waste disposal, especially in humid environments. Structural features such as folds, faults, and bedding and textural features such as formation permeability, porosity, and mineralogy all affect the water balance and water movement and, in turn, radionuclide migration. Where these features vary over short distance scales, detailed mapping is required in order to enable accurate model predictions of site performance and to provide the basis for proper design and planning of site-disposal operations

A preliminary study on the geochemical environment for deep geological disposal of high level radioactive waste in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Chun Soo; Bae, Dae Seok; Kim, Kyung Su; Koh, Yong Kwon; Park, Byoung Yun

2000-03-01

Geochemical study on the groundwater from crystalline rocks (granite and gneiss) for the deep geological disposal of high-level radioactive waste was carried out in order to elucidate the hydrogeochemical and isotope characteristics and geochemical evolution of the groundwater. Study areas are Jungwon, Chojeong, Youngcheon and Yusung for granite region, Cheongyang for gneiss region, and Yeosu for volcanic region. Groundwaters of each study areas weree sampled and analysed systematically. Groundwaters can be grouped by their chemistry and host rock. Origin of the groundwater was proposed by isotope ({sup 18}O, {sup 2}H, {sup 13}C, {sup 34}S, {sup 87}Sr, {sup 15}N) studies and the age of groundwater was inferred from their tritium contents. Based ont the geochemical and isotope characteristics, the geochemical evolutions of each types of groundwater were simulated using SOLVEQ/CHILLER and PHREEQC programs.

International safeguards relevant to geologic disposal of high-level wastes and spent fuels

International Nuclear Information System (INIS)

Pillay, K.K.S.; Picard, R.R.

1989-01-01

Spent fuels from once-through fuel cycles placed in underground repositories have the potential to become attractive targets for diversion and/or theft because of their valuable material content and decreasing radioactivity. The first geologic repository in the US, as currently designed, will contain approximately 500 Mt of plutonium, 60,000 Mt of uranium and a host of other fissile and strategically important elements. This paper identifies some of the international safeguards issues relevant to the various proposed scenarios for disposing of the spent fuel. In the context of the US program for geologic disposal of spent fuels, this paper highlights several issues that should be addressed in the near term by US industries, the Department of Energy, and the Nuclear Regulatory Commission before the geologic repositories for spent fuels become a reality. Based on US spent fuel discharges, an example is presented to illustrate the enormity of the problem of verifying spent fuel inventories. The geologic disposal scenario for high-level wastes originating from defense facilities produced a ''practicably irrecoverable'' waste form. Therefore, safeguards issues for geologic disposal of high-level waste now in the US are less pressing. 56 refs. , 2 figs

How to Shape a Successful Repository Program: Staged Development of Geologic Repositories for High-Level Waste

International Nuclear Information System (INIS)

Isaacs, T.

2004-01-01

Programs to manage and ultimately dispose of high-level radioactive wastes are unique from scientific and technological as well as socio-political aspects. From a scientific and technological perspective, high-level radioactive wastes remain potentially hazardous for geological time periods--many millennia--and scientific and technological programs must be put in place that result in a system that provides high confidence that the wastes will be isolated from the accessible environment for these many thousands of years. Of course, ''proof'' in the classical sense is not possible at the outset, since the performance of the system can only be known with assurance, if ever, after the waste has been emplaced for those geological time periods. Adding to this challenge, many uncertainties exist in both the natural and engineered systems that are intended to isolate the wastes, and some of the uncertainties will remain regardless of the time and expense in attempting to characterize the system and assess its performance

How to Shape a Successful Repository Program: Staged Development of Geologic Repositories for High-Level Waste

Energy Technology Data Exchange (ETDEWEB)

Isaacs, T.

2004-10-03

Programs to manage and ultimately dispose of high-level radioactive wastes are unique from scientific and technological as well as socio-political aspects. From a scientific and technological perspective, high-level radioactive wastes remain potentially hazardous for geological time periods--many millennia--and scientific and technological programs must be put in place that result in a system that provides high confidence that the wastes will be isolated from the accessible environment for these many thousands of years. Of course, ''proof'' in the classical sense is not possible at the outset, since the performance of the system can only be known with assurance, if ever, after the waste has been emplaced for those geological time periods. Adding to this challenge, many uncertainties exist in both the natural and engineered systems that are intended to isolate the wastes, and some of the uncertainties will remain regardless of the time and expense in attempting to characterize the system and assess its performance.

Interfaces between transport and geological disposal systems for high level radioactive waste and spent nuclear fuel

International Nuclear Information System (INIS)

1994-09-01

This document is an IAEA publication which identifies and discusses the interfaces and the interface requirements between high level waste, the waste transport system used for carriage of the waste to the disposal facility, and the high level waste disposal facility. The development of this document was prompted in part by the initiatives in various Member States to select, characterize and design the facilities for potential high level waste geological repositories. These initiatives have progressed to the point where an international document would be useful in calling attention to the need for establishing, in a systematic way, interfaces and interface requirements between the transport systems to be used and the waste disposal packages and geological repository. Refs, figs and tabs

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

Confidence improvement of disosal safety bydevelopement of a safety case for high-level radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Baik, Min Hoon; Ko, Nak Youl; Jeong, Jong Tae; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

Many countries have developed a safety case suitable to their own countries in order to improve the confidence of disposal safety in deep geological disposal of high-level radioactive waste as well as to develop a disposal program and obtain its license. This study introduces and summarizes the meaning, necessity, and development process of the safety case for radioactive waste disposal. The disposal safety is also discussed in various aspects of the safety case. In addition, the status of safety case development in the foreign countries is briefly introduced for Switzerland, Japan, the United States of America, Sweden, and Finland. The strategy for the safety case development that is being developed by KAERI is also briefly introduced. Based on the safety case, we analyze the efforts necessary to improve confidence in disposal safety for high-level radioactive waste. Considering domestic situations, we propose and discuss some implementing methods for the improvement of disposal safety, such as construction of a reliable information database, understanding of processes related to safety, reduction of uncertainties in safety assessment, communication with stakeholders, and ensuring justice and transparency. This study will contribute to the understanding of the safety case for deep geological disposal and to improving confidence in disposal safety through the development of the safety case in Korea for the disposal of high-level radioactive waste.

40 CFR 227.30 - High-level radioactive waste.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false High-level radioactive waste. 227.30...-level radioactive waste. High-level radioactive waste means the aqueous waste resulting from the operation of the first cycle solvent extraction system, or equivalent, and the concentrated waste from...

Geology of the Yucca Mountain Region, Chapter in Stuckless, J.S., ED., Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

J.S. Stuckless; D. O' Leary

2006-09-25

Yucca Mountain has been proposed as the site for the Nation's first geologic repository for high-level radioactive waste. This chapter provides the geologic framework for the Yucca Mountain region. The regional geologic units range in age from late Precambrian through Holocene, and these are described briefly. Yucca Mountain is composed dominantly of pyroclastic units that range in age from 11.4 to 15.2 Ma. The proposed repository would be constructed within the Topopah Spring Tuff, which is the lower of two major zoned and welded ash-flow tuffs within the Paintbrush Group. The two welded tuffs are separated by the partly to nonwelded Pah Canyon Tuff and Yucca Mountain Tuff, which together figure prominently in the hydrology of the unsaturated zone. The Quaternary deposits are primarily alluvial sediments with minor basaltic cinder cones and flows. Both have been studied extensively because of their importance in predicting the long-term performance of the proposed repository. Basaltic volcanism began about 10 Ma and continued as recently as about 80 ka with the eruption of cones and flows at Lathrop Wells, approximately 10 km south-southwest of Yucca Mountain. Geologic structure in the Yucca Mountain region is complex. During the latest Paleozoic and Mesozoic, strong compressional forces caused tight folding and thrust faulting. The present regional setting is one of extension, and normal faulting has been active from the Miocene through to the present. There are three major local tectonic domains: (1) Basin and Range, (2) Walker Lane, and (3) Inyo-Mono. Each domain has an effect on the stability of Yucca Mountain.

Radioactive waste disposal programme and siting regions for geological deep repositories. Executive summary. November 2008

International Nuclear Information System (INIS)

2008-11-01

There are radioactive wastes in Switzerland. Since many decades they are produced by the operation of the five nuclear power plants, by medicine, industry and research. Important steps towards the disposal of these wastes are already realized; the corresponding activities are practised. This particularly concerns handling and packaging of the radioactive wastes, their characterization and inventory, as well as the interim storage and the inferred transportations. Preparatory works in the field of scientific research on deep geological repositories have allowed to acquire high level of technical and scientific expertise in that domain. The feasibility of building long-term safe geological repositories in Switzerland was demonstrated for all types of radioactive wastes; the demonstration was accepted by the Federal Council. There is enough knowledge to propose geological siting regions for further works. The financial funds already accumulated guaranty the financing of the dismantling of the power plants as well as building deep geological repositories for the radioactive wastes. The regulations already exist and the organisational arrangements necessary for the fruitful continuation of the works already done have been taken. The programme of the disposal of radioactive wastes also describes the next stages towards the timely realization of the deep repositories as well as the level of the financial needs. The programme is updated every five years, checked by the regulatory bodies and accepted by the Federal Council who reports to the parliament. The process of choosing a site, which will be completed in the next years, is detailed in the conceptual part of the programme for deep geological repositories. The NAGRA proposals are based exclusively on technical and scientific considerations; the global evaluation taking into account also political considerations has to be performed by the authorities and the Federal Council. The programme states that at the beginning of

Issues related to the USEPA probabilistic standard for geologic disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Okrent, D.

1993-01-01

This paper asks whether some of the fundamental bases for the 1985 USEPA standard on disposal of high level radioactive wastes (40 CFR Part 191) warrant re-examination. Similar questions also apply to the bases for the radioactive waste disposal requirements proposed by most other countries. It is suggested that the issue of intergenerational equity has been dealt with from too narrow a perspective. Not only should radioactive and nonradioactive hazardous waste disposal be regulated from a consistent philosophic basis, but the regulation of waste disposal itself should be embedded in the broader issues of intergenerational conservation of options, conservation of quality, and conservation of access. (author). 25 refs

Feasibility of disposal of high-level radioactive waste into the seabed. Volume 4: Engineering

International Nuclear Information System (INIS)

Hickerson, J.; Freeman, T.J.; Boisson, J.Y.; Murray, C.N.; Gera, F.; Nakamura, H.; Nieuwenhuis, J.D.; Schaller, K.H.

1988-01-01

One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This report summarizes work performed to develop and evaluate engineering methods of emplacing high level radioactive waste in stable, deep ocean sediments. It includes results of desktop studies, laboratory experiments and field tests conducted in deep water

Handbook of high-level radioactive waste transportation

International Nuclear Information System (INIS)

Sattler, L.R.

1992-10-01

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government's system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government's program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project

JNC thermodynamic database for performance assessment of high-level radioactive waste disposal system

Energy Technology Data Exchange (ETDEWEB)

Yui, Mikazu; Azuma, Jiro; Shibata, Masahiro [Japan Nuclear Cycle Development Inst., Tokai Works, Waste Isolation Research Division, Tokai, Ibaraki (Japan)

1999-11-01

This report is a summary of status, frozen datasets, and future tasks of the JNC (Japan Nuclear Cycle Development Institute) thermodynamic database (JNC-TDB) for assessing performance of high-level radioactive waste in geological environments. The JNC-TDB development was carried out after the first progress report on geological disposal research in Japan (H-3). In the development, thermodynamic data (equilibrium constants at 25degC, I=0) for important radioactive elements were selected/determined based on original experimental data using different models (e.g., SIT, Pitzer). As a result, the reliability and traceability of the data for most of the important elements were improved over those of the PNC-TDB used in H-3 report. For detailed information of data analysis and selections for each element, see the JNC technical reports listed in this document. (author)

Evaluated and estimated solubility of some elements for performance assessment of geological disposal of high-level radioactive waste using updated version of thermodynamic database

International Nuclear Information System (INIS)

Kitamura, Akira; Doi, Reisuke; Yoshida, Yasushi

2011-01-01

Japan Atomic Energy Agency (JAEA) established the thermodynamic database (JAEA-TDB) for performance assessment of geological disposal of high-level radioactive waste (HLW) and TRU waste. Twenty-five elements which were important for the performance assessment of geological disposal were selected for the database. JAEA-TDB enhanced reliability of evaluation and estimation of their solubility through selecting the latest and the most reliable thermodynamic data at present. We evaluated and estimated solubility of the 25 elements in the simulated porewaters established in the 'Second Progress Report for Safety Assessment of Geological Disposal of HLW in Japan' using the JAEA-TDB and compared with those using the previous thermodynamic database (JNC-TDB). It was found that most of the evaluated and estimated solubility values were not changed drastically, but the solubility and speciation of dominant aqueous species for some elements using the JAEA-TDB were different from those using the JNC-TDB. We discussed about how to provide reliable solubility values for the performance assessment. (author)

Corrosion models for predictions of performance of high-level radioactive-waste containers

Energy Technology Data Exchange (ETDEWEB)

Farmer, J.C.; McCright, R.D. [Lawrence Livermore National Lab., CA (United States); Gdowski, G.E. [KMI Energy Services, Livermore, CA (United States)

1991-11-01

The present plan for disposal of high-level radioactive waste in the US is to seal it in containers before emplacement in a geologic repository. A proposed site at Yucca Mountain, Nevada, is being evaluated for its suitability as a geologic repository. The containers will probably be made of either an austenitic or a copper-based alloy. Models of alloy degradation are being used to predict the long-term performance of the containers under repository conditions. The models are of uniform oxidation and corrosion, localized corrosion, and stress corrosion cracking, and are applicable to worst-case scenarios of container degradation. This paper reviews several of the models.

Human intrusion into geologic repositories for high-level radioactive waste: potential and prevention

Energy Technology Data Exchange (ETDEWEB)

Cameron, F X [Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research

1981-12-01

Isolation of high-level radioactive waste over long periods of time requires protection not only from natural events and processes, but also from the deliberate or inadvertent activities of future societies. This paper evaluates the likelihood of inadvertent human intrusion due to the loss of societal memory of the repository site. In addition measures to prevent inadvertent intrusion, and to guide future societies in any decision to deliberately intrude into the repository are suggested.

Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

International Nuclear Information System (INIS)

Jantzen, C.M.

1994-01-01

Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control

Project Guarantee 1985. Final repository for high-level radioactive wastes: The system of safety barriers

International Nuclear Information System (INIS)

Anon.

1985-01-01

Final disposal of radioactive waste involves preventing the waste from returning from the repository location into the biosphere by means of successively arranged containment measures known as safety barriers. In the present volume NGB 85-04 of the series of reports for Project 'Guarantee' 1985, the safety barrier system for the type C repository for high-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). Safety barriers take the form of both technically constructed containment measures and the siting of the repository in suitable geological formations. The technical safety barrier system in the case of high-level waste comprises: the waste solidification matrix (borosilicate glass), massive steel canisters, encasement of the waste canisters, encasement of the waste canisters in highly compacted bentonite, sealing of vacant storage space and access routes on repository closure. The natural geological safety barriers - the host rock and overlying formations provide sufficiently long deep groundwater flow times from the repository location to the earth's surface and for additional lengthening of radionuclide migration times by means of various chemical and physical retardation mechanisms. The stability of the geological formations is so great that hydrogeological system is protected for a sufficient length of time from deterioration caused, in particular, by erosion. Observations in the final section of the report indicate that input data for the type C repository safety

Uncertainty analysis for geologic disposal of radioactive waste

International Nuclear Information System (INIS)

Cranwell, R.M.; Helton, J.C.

1981-01-01

The incorporation and representation of uncertainty in the analysis of the consequences and risks associated with the geologic disposal of high-level radioactive waste are discussed. Such uncertainty has three primary components: process modeling uncertainty, model input data uncertainty, and scenario uncertainty. The following topics are considered in connection with the preceding components: propagation of uncertainty in the modeling of a disposal site, sampling of input data for models, and uncertainty associated with model output

Parametric analysis of mined geologic disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Parker, F.L.; Ichel, A.

1982-01-01

A simplified mathematical model has been developed to screen potential mined geological repository sites taking into account the uncertainty in the input data. Initial input data that was assumed constant was inventory of radioactive wastes, number and size of cannisters, size of repository, and the ground water flow area. Though there is some uncertainty in these data, by far the greatest uncertainty pertained to leach rate of the waste form and cannister, ground water velocity, retardation rates of nuclides relative to ground water, distance to the biosphere and flow rate in the receiving waters in the biosphere. These were varied over realistic ranges from 1 to 4 orders of magnitude. The results showed that there are a wide variety of combinations of these parameters that allow a waste repository to be sited without exceeding the maximum permissible concentrations of isotopes in drinking water. It is concluded that for the artificially-created nuclides it is the intermediate time period, greater than 1000 years and less than 1 million years, that poses the greatest problem

Staff analysis of public comments on proposed rule 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories

International Nuclear Information System (INIS)

1983-12-01

On February 25, 1981, the Nuclear Regulatory Commission published rules which establish procedures for the licensing of geologic disposal, by the US Department of Energy, of high-level radioactive wastes. On July 8, 1981, proposed technical criteria which would be used in the evaluation of license applications under those procedural rules were published in the Federal Register. The Commission received 93 comment letters on the proposed technical criteria, 89 of which were received in time for the Commission to consider in preparing the final technical criteria which were published on June 21, 1983. This document presents a detailed analysis of the comments received on the proposed rule by the Commission's staff and also contains the Rationale for the Performance Objectives of 10 CFR Part 60

Rethinking high-level radioactive waste disposal: making the safety case

International Nuclear Information System (INIS)

Parker, F.L.

1991-01-01

There is worldwide consensus that geological disposal is best for disposing of high-level radioactive waste; nevertheless, the U.S. program is unlikely to succeed. The program is hampered by its high degree of inflexibility with respect to both schedule and technical specifications that assume the properties and future behavior of a geological repository can be determined and specified with a very high degree of certainty. Geological models, and scientific knowledge generally, have been inappropriately applied. Geophysical analysis can and should have a key role in the assessment of long-term repository isolation; however, geophysial models are being asked to predict the detailed structure and behavior of sites over thousands of years. This is scientifically unsound and will lead to bad engineering practice. The United States has written detailed regulations for repository siting and construction before all of the data are in and is thus bound by requirements that may be impossible to meet. An alternative approach emphasizing flexibility can succeed. It will require time to assess performance, a willingness to respond to problems as they arise, remediation if necessary, and revision of the design and regulations if they are found to impede progress toward the health goal already defined as safe disposal. 6 refs

Analogues to features and processes of a high-level radioactive waste repository proposed for Yucca Mountain, Nevada

Science.gov (United States)

Simmons, Ardyth M.; Stuckless, John S.; with a Foreword by Abraham Van Luik, U.S. Department of Energy

2010-01-01

Natural analogues are defined for this report as naturally occurring or anthropogenic systems in which processes similar to those expected to occur in a nuclear waste repository are thought to have taken place over time periods of decades to millennia and on spatial scales as much as tens of kilometers. Analogues provide an important temporal and spatial dimension that cannot be tested by laboratory or field-scale experiments. Analogues provide one of the multiple lines of evidence intended to increase confidence in the safe geologic disposal of high-level radioactive waste. Although the work in this report was completed specifically for Yucca Mountain, Nevada, as the proposed geologic repository for high-level radioactive waste under the U.S. Nuclear Waste Policy Act, the applicability of the science, analyses, and interpretations is not limited to a specific site. Natural and anthropogenic analogues have provided and can continue to provide value in understanding features and processes of importance across a wide variety of topics in addressing the challenges of geologic isolation of radioactive waste and also as a contribution to scientific investigations unrelated to waste disposal. Isolation of radioactive waste at a mined geologic repository would be through a combination of natural features and engineered barriers. In this report we examine analogues to many of the various components of the Yucca Mountain system, including the preservation of materials in unsaturated environments, flow of water through unsaturated volcanic tuff, seepage into repository drifts, repository drift stability, stability and alteration of waste forms and components of the engineered barrier system, and transport of radionuclides through unsaturated and saturated rock zones.

Geological disposal of radioactive waste. Safety requirements

International Nuclear Information System (INIS)

2006-01-01

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

Status of technology for isolating high-level radioactive wastes in geologic repositories

International Nuclear Information System (INIS)

Klingsberg, C.; Duguid, J.

1980-10-01

This report attempts to summarize the status of scientific and technological knowledge relevant to long-term isolation of high-level and transuranic wastes in a mined geologic repository. It also identifies and evaluates needed information and identifies topics in which work is under way or needed to reduce uncertainties. The major findings and conclusions on the following topics are presented: importance of the systems approach; prospects for successful isolation of wastes; need for site-specific investigations; human activities in the future; importance of modelling; disposal of transuranic wastes; status of technology of isolation barriers, performance assessment, site selection and characterization, and potential host rocks

King's Trough Flank: geological and geophysical investigations of its suitability for high-level radioactive waste disposal

International Nuclear Information System (INIS)

Kidd, R.B.; Searle, R.C.; Weaver, P.P.E.; Jacobs, C.L.; Huggett, Q.J.; Noel, M.J.; Schultheiss, P.J.

1983-01-01

The King's Trough Flank study area in the Northeast Atlantic Ocean was chosen in 1979 as a location at which to examine the suitability of pelagic carbonate sequences for sub-seabed disposal of high-level radioactive waste. This report summarises investigations up to the end of 1982; following visits by four research ships to the area during which geophysical data and sediment samples were collected. The region is a characteristically rugged portion of the deep ocean floor with hills and scarps 10 to 30 km apart and slopes around the hills ranging from 18 deg to 30 deg. Areas of relatively smooth seafloor occur, however, up to 35 km across, where slopes no greater than 2 deg are recorded. At this stage an apparent discrepancy between the geophysical and sediment core data leaves some uncertainty regarding the stability of the sediment cover and the likelihood of current erosion in these areas. The general suitability of the area is discussed by comparing our present geological and geophysical data with the set of 'desirable characteristics' for a sub-seabed disposal site first outlined in 1979. The difficulties involved in extrapolating findings from presently-sampled depths of up to 10 metres to depths envisaged for shallow waste disposal are emphasised. (author)

A new integrated approach to demonstrate the safe disposal of high-level radioactive waste and spent nuclear fuel in a geological repository

International Nuclear Information System (INIS)

Mueller-Hoeppe, N.; Krone, J.; Niehues, N.; Raitz von Frentz, R.

2000-01-01

Multi-barrier systems are accepted as the basic approach for long term environmental safe isolation of radioactive waste in geological repositories. Assessing the performance of natural and engineered barriers is one of the major difficulties in producing evidence of environmental safety for any radioactive waste disposal facility, due to the enormous complexity of scenarios and uncertainties to be considered. This paper outlines a new methodological approach originally developed basically for a repository in salt, but that can be transferred with minor modifications to any other host rock formation. The approach is based on the integration of following elements: (1) Implementation of a simple method and efficient criteria to assess and prove the tightness of geological and engineered barriers; (2) Using the method of Partial Safety Factors in order to assess barrier performance at certain reasonable level of confidence; (3) Integration of a diverse geochemical barrier in the near field of waste emplacement limiting systematically the radiological consequences from any radionuclide release in safety investigations and (4) Risk based approach for the assessment of radionuclide releases. Indicative calculations performed with extremely conservative assumptions allowed to exclude any radiological health consequences from a HLW repository in salt to a reference person with a safety level of 99,9999% per year. (author)

Research on advanced technology of performance assessment for geological disposal of high-level radioactive waste (Joint research)

International Nuclear Information System (INIS)

2006-12-01

JAEA and RWMC have carried out a joint research program on advanced technologies that could be used to support performance assessments of geological disposal concepts for high-level radioactive waste. The following 5 items were considered in the program: 1) planning of a basic strategy for the development of analysis technologies on nuclide migration over various spatial and temporal scales; 2) development of analysis technologies for vitrified waste scale; 3) development of analysis technologies for repository scale; 4) development of integration technologies for geochemical information; and 5) development of technologies to promote the logical understanding of repository performance and safety. The above items were discussed in the context of technological experiences gained by JAEA and RWMC in previous repository-related studies. According to the results of these discussions, development strategies for each of the technology areas identified above were efficiently formulated by appropriate task allocations. Specific technical subjects requiring further investigation were also identified using this approach, and potential feed-backs from the results of these investigations into the overall research plan and strategy were considered. These specific research and development subjects in the overall strategy defined by this project should be implemented in the future. (author)

Adapting the notion of natural (geological) barrier for final disposal of low- and intermediate-level radioactive wastes in Romania

International Nuclear Information System (INIS)

Durdun, I.; Marunteanu, C.; Andrei, V.

2001-01-01

According to the Minimum Disturbances Design (MDD) notion by Carl-Olof Morfeldt of Mineconsult, Sweden, any site selection, design and construction of low- and intermediate-level radioactive waste repository should be based on a thorough knowledge of the geological environmental so that the implantation of the disposal facility induce no significant harmful consequences. This work presents the way in which the Romanian program of radioactive waste management was implemented for disposal of low- and intermediate-level radioactive wastes from Cernavoda NPP. Based on geological criteria of selection of lithologic, petrographic, tectonic, seismologic, hydrologic and geo-technic nature, 37 sites were analyzed from which 2 were retained and finally one, Saligny site, was chosen, as the most close to Cernavoda NPP. Also, public acceptance and transport connections were taken into consideration. SUTRA, SWMS-2D and CHAIN-2D codes were applied to analyze the safety and the geological barrier effects. The barrier consists in red clay, a smectitic mineralogic compound. The computation showed that in Saligny vault the maximal tritium extension is kept inside due to the red clay barrier. Geo-technical engineering works were conducted to improve the properties of the loess upper layer which resulted in lowering its sensitivity to moistening and erosion

Disposal of high level and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Flowers, R.H.

1991-01-01

The waste products from the nuclear industry are relatively small in volume. Apart from a few minor gaseous and liquid waste streams, containing readily dispersible elements of low radiotoxicity, all these products are processed into stable solid packages for disposal in underground repositories. Because the volumes are small, and because radioactive wastes are latecomers on the industrial scene, a whole new industry with a world-wide technological infrastructure has grown up alongside the nuclear power industry to carry out the waste processing and disposal to very high standards. Some of the technical approaches used, and the Regulatory controls which have been developed, will undoubtedly find application in the future to the management of non-radioactive toxic wastes. The repository site outlined would contain even high-level radioactive wastes and spent fuels being contained without significant radiation dose rates to the public. Water pathway dose rates are likely to be lowest for vitrified high-level wastes with spent PWR fuel and intermediate level wastes being somewhat higher. (author)

Status report on the Nuclear Regulatory Commission regulations for land disposal of low-level radioactive wastes and geologic repository disposal of high-level wastes

International Nuclear Information System (INIS)

Browning, R.E.; Bell, M.J.; Dragonette, K.S.; Johnson, T.C.; Roles, G.W.; Lohaus, P.H.; Regnier, E.P.

1984-01-01

On 27 December 1982, the United States Nuclear Regulatory Commission (NRC) amended its regulations to provide specific requirements for licensing the land disposal of low-level radioactive wastes. The regulations establish performance objectives for land disposal of waste; technical requirements for the siting, design, operations, and closure activities for a near-surface disposal facility; technical requirements concerning waste form and classification that waste generators must meet for the land disposal of waste; institutional requirements; financial assurance requirements; and administrative and procedural requirements for licensing a disposal facility. Waste generators must comply with the waste form and classification provisions of the new rule, on 27 December 1983, one year later. During this implementation period, licensees must develop programmes to ensure compliance with the new waste form and classification provisions. The NRC is also promulgating regulations specifying the technical criteria for disposal of high-level radioactive wastes in geological repositories. The proposed rule was published for public comment in July 1981. Public comments have been received and considered by the Commission staff. The Commission will soon approve and publish a revised final rule. While the final rule being considered by the Commission is fundamentally the same as the proposed rule, provisions have been added to permit flexibility in the application of numerical criteria, some detailed design requirements have been deleted, and other changes have been made in response to comments. The rule is consistent with the recently enacted Nuclear Waste Policy Act of 1982. (author)

Final repositories for high-level radioactive waste; Endlagerung hochradioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-10-15

The brochure on final repositories for high-level radioactive waste covers the following issues: What is the origin of radioactive wastes? How large are the waste amounts? What is going to happen with the wastes? What is the solution for the Waste disposal? A new site search is started. Safety requirements for the final disposal of high-level radioactive wastes. Comparison of host rocks. Who is responsible and who will pay? Final disposal of high-level radioactive wastes worldwide. Short summary: History of the search for a final repository for high-level radioactive wastes in Germany.

Risk methodology for geologic disposal of radioactive waste

International Nuclear Information System (INIS)

Cranwell, R.M.; Campbell, J.E.; Ortiz, N.R.; Guzowski, R.V.

1990-04-01

This report contains the description of a procedure for selecting scenarios that are potentially important to the isolation of high- level radioactive wastes in deep geologic formations. In this report, the term scenario is used to represent a set of naturally occurring and/or human-induced conditions that represent realistic future states of the repository, geologic systems, and ground-water flow systems that might affect the release and transport of radionuclides from the repository to humans. The scenario selection procedure discussed in this report is demonstrated by applying it to the analysis of a hypothetical waste disposal site containing a bedded-salt formation as the host medium for the repository. A final set of 12 scenarios is selected for this site. 52 refs., 48 figs., 5 tabs

Studies for geologic storage of radioactive waste in the southeast

International Nuclear Information System (INIS)

Marine, I.W.

1977-01-01

The National Waste Terminal Storage (NWTS) program was initiated to conduct the research necessary to select a site for a geologic repository for the storage of high-level, solidified radioactive waste from commercial power reactors. The program also includes the design and construction of the facility and its operation once completed. As part of this program, the Savannah River Laboratory is conducting geological research that is particularly relevant to potential repository sites in the Southeast, but is also of generic applicability. This paper describes the National Waste Terminal Storage program as well as the research program at the Savannah River Laboratory

Studies for geologic storage of radioactive waste in the southeast

International Nuclear Information System (INIS)

Marine, I.W.

1978-01-01

The National Waste Terminal Storage (NWTS) program was initiated to conduct the research necessary to select a site for a geologic repository for the storage of high-level, solidified radioactive waste from commercial power reactors. The program also includes the design and construction of the facility and its operation once completed. As part of this program, the Savannah River Laboratory is conducting geological research that is particularly relevant to potential repository sites in the southeast, but is also of generic applicability. This paper describes the National Waste Terminal Storage program as well as the research program at the Savannah River Laboratory. 31 figures

United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management

International Nuclear Information System (INIS)

Stewart, L.

2004-01-01

The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas

High-Level Radioactive Waste.

Science.gov (United States)

Hayden, Howard C.

1995-01-01

Presents a method to calculate the amount of high-level radioactive waste by taking into consideration the following factors: the fission process that yields the waste, identification of the waste, the energy required to run a 1-GWe plant for one year, and the uranium mass required to produce that energy. Briefly discusses waste disposal and…

High-level radioactive wastes

International Nuclear Information System (INIS)

Grissom, M.C.

1982-10-01

This bibliography contains 812 citations on high-level radioactive wastes included in the Department of Energy's Energy Data Base from January 1981 through July 1982. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

Disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Glasby, G.P.

1977-01-01

Although controversy surrounding the possible introduction of nuclear power into New Zealand has raised many points including radiation hazards, reactor safety, capital costs, sources of uranium and earthquake risks on the one hand versus energy conservation and alternative sources of energy on the other, one problem remains paramount and is of global significance - the storage and dumping of the high-level radioactive wastes of the reactor core. The generation of abundant supplies of energy now in return for the storage of these long-lived highly radioactive wastes has been dubbed the so-called Faustian bargain. This article discusses the growth of the nuclear industry and its implications to high-level waste disposal particularly in the deep-sea bed. (auth.)

Operation environment construction of geological information database for high level radioactive waste geological disposal

International Nuclear Information System (INIS)

Wang Peng; Gao Min; Huang Shutao; Wang Shuhong; Zhao Yongan

2014-01-01

To fulfill the requirements of data storage and management in HLW geological disposal, a targeted construction method for data operation environment was proposed in this paper. The geological information database operation environment constructed by this method has its unique features. And it also will be the important support for HLW geological disposal project and management. (authors)

Problems and approach to geological disposal of radioactive waste

International Nuclear Information System (INIS)

Kitayama, Kazumi; Yamazaki, Haruo; Ijiri, Yuji; Haga, Kazuko; Sakamaki, Masanori; Kishi, Kiyoshi

2006-01-01

This feature articles described a concept and technical problems of geological disposal of high-level radioactive waste in the civil engineering. It consists of six papers such as the present statues and subjects of geological disposal by KITAYAMA Kazumi, the diastrophism, igneous activity, and upheaval and erosion by YAMAZAKI Haruo, the groundwater flow and evaluation of nuclear transfer by IJIRI Yuji, evaluation of alteration of cement materials in the ultra-long period by HAGA Kazuko, The Mizunami Underground Research Laboratory in course of construction by SAKAMAKI Masanori, and interview of the ninetieth president of JSCE (Japan Society of Civil Engineers), he places his hope on JSCE and civil engineers by KISHI Kiyoshi. (S.Y.)

A thermoelectric-conversion power supply system using a strontium heat source of high-level radioactive nuclear waste

International Nuclear Information System (INIS)

Chikazawa, Yoshitaka

2011-01-01

A thermoelectric-conversion power supply system with radioactive strontium in high-level radioactive waste has been proposed. A combination of Alkali Metal Thermo-Electric Conversion (AMTEC) and a strontium fluoride heat source can provide a compact and long-lived power supply system. A heat source design with strontium fluoride pin bundles with Hastelloy cladding and intermediate copper has been proposed. This design has taken heat transportation into consideration, and, in this regard, the feasibility has been confirmed by a three-dimensional thermal analysis using Star-CD code. This power supply system with an electric output of 1 MW can be arranged in a space of 50 m 2 and approximately 1.1 m height and can be operated for 15 years without refueling. This compact and long-lived power supply is suitable for powering sources for remote places and middle-sized ships. From the viewpoint of geological disposal of high-level waste, the proposed power supply system provides a financial base for strontium-cesium partitioning. That is, a combination of minor-actinide recycling and strontium-cesium partitioning can eliminate a large part of decay heat in high-level waste and thus can save much space for geological disposal. (author)

Methods for estimating costs of transporting spent fuel and defense high-level radioactive waste for the civilian radioactive waste management program

International Nuclear Information System (INIS)

Darrough, M.E.; Lilly, M.J.

1989-01-01

The US Department of Energy (DOE), through the Office of Civilian Radioactive Waste Management, is planning and developing a transportation program for the shipment of spent fuel and defense high-level waste from current storage locations to the site of the mined geologic repository. In addition to its responsibility for providing a safe transportation system, the DOE will assure that the transportation program will function with the other system components to create an integrated waste management system. In meeting these objectives, the DOE will use private industry to the maximum extent practicable and in a manner that is cost effective. This paper discusses various methodologies used for estimating costs for the national radioactive waste transportation system. Estimating these transportation costs is a complex effort, as the high-level radioactive waste transportation system, itself, will be complex. Spent fuel and high-level waste will be transported from more than 100 nuclear power plants and defense sites across the continental US, using multiple transport modes (truck, rail, and barge/rail) and varying sizes and types of casks. Advance notification to corridor states will be given and scheduling will need to be coordinated with utilities, carriers, state and local officials, and the DOE waste acceptance facilities. Additionally, the waste forms will vary in terms of reactor type, size, weight, age, radioactivity, and temperature

Alternatives evaluation of high activity radioactive wastes disposal

International Nuclear Information System (INIS)

Ciallella, N.R.; Petraitis, E.J.

1989-01-01

Different alternatives considered in the world to be used as barriers to isolate the high level radioactive from the environment wastes produced during the electric energy generation of nuclear origin are presented. Engineering and geologic barriers, are analyzed, considering nuclear fuel cycles with or without plutonium recycling; to that purpose the consideration of elements such as durability and resistance of the various engineering, availability of the fabrication processes, associated radiological impact, geological media apt to be used as geological barrier. Finally, the scopes of the Feasibility Study and Engineering draft are presented for the construction of a repository for high-level radioactive wastes, for the Argentine Nuclear Program needs, which contemplates the construction of six nuclear power plants with a potential installed towards the year 2000 GW( e ), with natural and/or lowly enriched uranium power plants and recycling of plutonium generated in the cycle. (Author) [es

Risk management and organizational systems for high-level radioactive waste disposal: Issues and priorities

International Nuclear Information System (INIS)

Emel, J.; Cook, B.; Kasperson, R.; Brown, H.; Guble, R.; Himmelberger, J.; Tuller, S.

1988-09-01

The discussion to follow explores the nature of the high-level radioactive waste disposal tasks and their implications for the design and organizational structure of effective risk management systems. We organize this discussion in a set of interrelated tasks that draw upon both relevant theory and accumulated experience. Specifically these tasks are to assess the management implications of the high levels of technical and social uncertainty that characterize the technology and mission; to identify the elements of organizational theory that bear upon risk management system design; to explore these theoretical issues in the context of two hypothetical risk scenarios associated with radioactive waste disposal; to consider the appropriate role of engineered and geological barriers; to examine briefly issues implicit in DOE's past waste management performance, with special attention to the Hanford facility; and to suggest findings and recommendations that require further attention. 74 refs

Reduction on high level radioactive waste volume and geological repository footprint with high burn-up and high thermal efficiency of HTGR

Energy Technology Data Exchange (ETDEWEB)

Fukaya, Yuji, E-mail: fukaya.yuji@jaea.go.jp; Nishihara, Tetsuo

2016-10-15

Highlights: • We evaluate the number of canisters and its footprint for HTGR. • We proposed new waste loading method for direct disposal of HTGR. • HTGR can significantly reduce HLW volume compared with LWR. - Abstract: Reduction on volume of High Level radioactive Waste (HLW) and footprint in a geological repository due to high burn-up and high thermal efficiency of High Temperature Gas-cooled Reactor (HTGR) has been investigated. A helium-cooled and graphite-moderated commercial HTGR was designed as a Gas Turbine High Temperature Reactor (GTHTR300), and that has particular features such as significantly high burn-up of approximately 120 GWd/t, high thermal efficiency around 50%, and pin-in-block type fuel. The pin-in-block type fuel was employed to reduce processed graphite volume in reprocessing. By applying the feature, effective waste loading method for direct disposal is proposed in this study. By taking into account these feature, the number of HLW canister generations and its repository footprint are evaluated by burn-up fuel composition, thermal calculation and criticality calculation in repository. As a result, it is found that the number of canisters and its repository footprint per electricity generation can be reduced by 60% compared with Light Water Reactor (LWR) representative case for direct disposal because of the higher burn-up, higher thermal efficiency, less TRU generation, and effective waste loading proposed in this study for HTGR. But, the reduced ratios change to 20% and 50% if the long term durability of LWR canister is guaranteed. For disposal with reprocessing, the number of canisters and its repository footprint per electricity generation can be reduced by 30% compared with LWR because of the 30% higher thermal efficiency of HTGR.

A modelling study for long-term life prediction of carbon steel overpack for geological isolation of High-Level Radioactive Waste

International Nuclear Information System (INIS)

Taniguchi, Naoki; Honda, Akira; Ishikawa, Hirohisa

1996-01-01

Current plans for the geological disposal of High-Level Radioactive Waste (HLW) in Japan include metal overpacks which contain HLW. Overpacks may be required to remain intact for more than several hundred years in order to provide containment of radio nuclides. The main factor limiting the performance of overpacks is considered to be corrosion by groundwater. Carbon steel is one of the candidate material for overpacks. A mathematical model for life prediction of carbon steel overpack has been developed based on corrosion mechanism. General corrosion and localized corrosion are considered because these are likely to initiate in repository conditions. In general corrosion model, the reduction of oxygen and water are considered as cathodic reaction. In localized corrosion model, we have constructed a model which predict the period for localized corrosion based on oxygen transport in bentonite. We also developed a model which predict the propagation rate of localized corrosion that is based on mass balance within the corroding cavity. (author)

High-level radioactive waste management in the United States. Background and status: 1996

International Nuclear Information System (INIS)

Dyer, J.R.

1996-01-01

The US high-level radioactive waste disposal program is investigating a site at Yucca Mountain, Nevada, to determine whether or not it is a suitable location for the development of a deep mined geologic repository. At this time, the US program is investigating a single site, although in the past, the program involved successive screening and comparison of alternate locations. The United States civilian reactor programs do not reprocess spent fuel; the high-level waste repository will be designed for the emplacement or spent fuel and a limited amount of vitrified high-level wastes from previous reprocessing in the US. The legislation enabling the US program also contains provisions for a Monitored Retrievable Storage facility, which could provide temporary storage of spent fuel accepted for disposal, and improve the flexibility of the repository development schedule

Basic rock properties for the thermo-hydro-mechanical analysis of a high-level radioactive waste repository

Energy Technology Data Exchange (ETDEWEB)

Kim, Jhin Wung; Kang, Chul Hyung

1999-04-01

Deep geological radioactive waste disposal is generally based on the isolation of the waste from the biosphere by multiple barriers. The host rock is one of these barriers which should provide a stable mechanical and chemical environment for the engineered barriers. In the evaluation of the safety of the high-level radioactive waste disposal systems, an important part of the safety analysis is an assessment of the coupling or interaction between thermal, hydrological, and mechanical effects. In order to do this assessment, adequate data on the characteristics of different host rocks are necessary. The properties of the rock and rock discontinuity are very complex and their values vary in a wide range. The accuracy of the result of the assessment depends on the values of these properties used. The present study is an attempt to bring together and condense data for the basic properties of various rock masses, which are needed in the thermo-hydro-mechanical analysis for the deep geological radioactive waste repository. The testing and measurement methods for these basic properties are also presented. Domestic data for deep geological media should be supplemented in the future, due to the insufficiency and the lack of accuracy of the data available at present. (author). 28 refs., 21 figs.

Basic rock properties for the thermo-hydro-mechanical analysis of a high-level radioactive waste repository

International Nuclear Information System (INIS)

Kim, Jhin Wung; Kang, Chul Hyung

1999-04-01

Deep geological radioactive waste disposal is generally based on the isolation of the waste from the biosphere by multiple barriers. The host rock is one of these barriers which should provide a stable mechanical and chemical environment for the engineered barriers. In the evaluation of the safety of the high-level radioactive waste disposal systems, an important part of the safety analysis is an assessment of the coupling or interaction between thermal, hydrological, and mechanical effects. In order to do this assessment, adequate data on the characteristics of different host rocks are necessary. The properties of the rock and rock discontinuity are very complex and their values vary in a wide range. The accuracy of the result of the assessment depends on the values of these properties used. The present study is an attempt to bring together and condense data for the basic properties of various rock masses, which are needed in the thermo-hydro-mechanical analysis for the deep geological radioactive waste repository. The testing and measurement methods for these basic properties are also presented. Domestic data for deep geological media should be supplemented in the future, due to the insufficiency and the lack of accuracy of the data available at present. (author). 28 refs., 21 figs

Options for the disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Mitchell, N.T.; Laughton, A.S.; Webb, G.A.M.

1977-01-01

The management of radioactive waste within the fuel cycle, especially the high-level wastes from reprocessing of nuclear fuel, is currently a matter of particular concern. In the short term (meaning a timescale of tens of years) management by engineered storage is considered to provide a satisfactory solution. Beyond this, however, the two main alternative options which are considered in the paper are: (a) disposal by burial into geologic formations on land; and (b) disposal by emplacement into or onto the seabed. Status of our present knowledge on the land and seabed disposal options is reviewed together with an assessment of the extent to which their reliability and safety can be judged on presently available information. Further information is needed on the environmental behaviour of radioactivity in the form of solidified waste in both situations in order to provide a more complete, scientific assessment. Work done so far has clarified the areas where further research is most needed - for instance modelling of the environmental transfer processes associated with the seabed option. This is discussed together with an indication of the research programmes which are now being pursued

Radioactive waste disposal process geological structure for the waste disposal

International Nuclear Information System (INIS)

Courtois, G.; Jaouen, C.

1983-01-01

The process described here consists to carry out the two phases of storage operation (intermediate and definitive) of radioactive wastes (especially the vitrified ones) in a geological dispositif (horizontal shafts) at an adequate deepness but suitable for a natural convection ventilation with fresh air from the land surface and moved only with the calorific heat released by the burried radioactive wastes when the radioactive decay has reached the adequate level, the shafts are totally and definitely occluded [fr

U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

Science.gov (United States)

Trask, N.J.; Stevens, P.R.

1991-01-01

The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

Technical support for GEIS: radioactive waste isoltaion in geologic formations. Volume 19. Thermal analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/19, ''Thermal Analyses,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the thermal impacts of the isolated high level and spent-fuel wastes in geologic formations. A detailed account of the methodologies employed is given as well as selected results of the analyses

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.)

System analysis methods for geological repository of high level radioactive waste in granite

International Nuclear Information System (INIS)

Chen Weiming; Wang Ju; Li Yunfeng; Jin Yuanxin; Zhao Honggang

2009-01-01

Taking Beishan granite site as an example, this paper proposes the conceptual and structural design of repository for high level radioactive waste at first. Then the function, structure, environment and evolution of the repository are described by the methodology of system analysis. Based on these designs and descriptions, a calculation model for the repository is developed with software GoldSim. At last, this calculation model is applied to emulate the space-time distribution of repository radiotoxicity, to analyze the sensitivity of parameters in the model, to optimize the design parameters, and to predict and assess the repository performance. The results of this study can provide technical supports for resources allocation and coordination of R and D projects. (authors)

FEBEX project: full-scale engineered barriers experiment for a deep geological repository for high level radioactive waste in crystalline host rock

Energy Technology Data Exchange (ETDEWEB)

Alberid, J; Barcala, J M; Campos, R; Cuevas, A M; Fernandez, E [Ciemat. Madrid (Spain)

2000-07-01

FEBEX has the multiple objective of demonstrating the feasibility of manufacturing, handling and constructing the engineered barriers and of developing codes for the thermo-hydro-mechanical and thermo-hydro-geochemical performance assessment of a deep geological repository for high level radioactive wastes. These objectives require integrated theoretical and experimental development work. The experimental work consists of three parts: an in situ test, a mock-up test and a series of laboratory tests. The experiments is based on the Spanish reference concept for crystalline rock, in which the waste capsules are placed horizontally in drifts surround by high density compacted bentonite blocks. In the two large-scale tests, the thermal effects of the wastes were simulated by means of heaters; hydration was natural in the in situ test and controlled in the mock-up test. The large-scale tests, with their monitoring systems, have been in operation for more than two years. the demonstration has been achieved in the in situ test and there are great expectation that numerical models sufficiently validated for the near-field performance assessment will be achieved. (Author)

High-level radioactive waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Liikala, R.C.

1974-01-01

High-level radioactive waste in the U.S. will be converted to an encapsulated solid and shipped to a Federal repository for retrievable storage for extended periods. Meanwhile the development of concepts for ultimate disposal of the waste which the Federal Government would manage is being actively pursued. A number of promising concepts have been proposed, for which there is high confidence that one or more will be suitable for long-term, ultimate disposal. Initial evaluations of technical (or theoretical) feasibility for the various waste disposal concepts show that in the broad category, (i.e., geologic, seabed, ice sheet, extraterrestrial, and transmutation) all meet the criteria for judging feasibility, though a few alternatives within these categories do not. Preliminary cost estimates show that, although many millions of dollars may be required, the cost for even the most exotic concepts is small relative to the total cost of electric power generation. For example, the cost estimates for terrestrial disposal concepts are less than 1 percent of the total generating costs. The cost for actinide transmutation is estimated at around 1 percent of generation costs, while actinide element disposal in space is less than 5 percent of generating costs. Thus neither technical feasibility nor cost seems to be a no-go factor in selecting a waste management system. The seabed, ice sheet, and space disposal concepts face international policy constraints. The information being developed currently in safety, environmental concern, and public response will be important factors in determining which concepts appear most promising for further development

Spent fuel and high-level radioactive waste storage

International Nuclear Information System (INIS)

Trigerman, S.

1988-06-01

The subject of spent fuel and high-level radioactive waste storage, is bibliographically reviewed. The review shows that in the majority of the countries, spent fuels and high-level radioactive wastes are planned to be stored for tens of years. Sites for final disposal of high-level radioactive wastes have not yet been found. A first final disposal facility is expected to come into operation in the United States of America by the year 2010. Other final disposal facilities are expected to come into operation in Germany, Sweden, Switzerland and Japan by the year 2020. Meanwhile , stress is placed upon the 'dry storage' method which is carried out successfully in a number of countries (Britain and France). In the United States of America spent fuels are stored in water pools while the 'dry storage' method is still being investigated. (Author)

The study of fracture mineralization and relationship with high level radioactive waste of deep geological repository

International Nuclear Information System (INIS)

Reyes, Cristina N.

2003-01-01

Extensive investigations of the Ordovician, Dinantian and Permo-Triassic rocks of the Sellafield area of northwest England were undertaken by United Kingdom Nirex Ltd. as a possible national site for geological disposal of intermediate and low-level radioactive waste. Very detailed studies of fracture mineralisation at Sellafield were thus put in hand by Nirex Ltd. and the results summarised by the British Geological Survey. Deep (up to 2 km) boreholes were put down with excellent core recovery. It is generally agreed that the most significant pathway for the escape of all but a very few radionuclides is by solution in and advection of groundwater. In this context, rock fracture systems are particularly important because they offer a potentially rapid pathway to the surface and the biosphere. One striking aspect of this work is that the fracture mineralisation seemingly records major and rapid fluctuations in redox conditions -sometimes during apparently continuous precipitation of cements (ferroan and non-ferroan calcites, dolomite). Carbonate cements record variations in Fe 2+ availability. Fe(III) precipitates also as oxide (hematite) and Fe(II) as sulphide (pyrite). This study focuses on these elements and valence states and also on Mn; another element susceptible to redox controls but known to respond differently from Fe. Shallow sub-surface stores or repositories would be more likely to have oxidising or fluctuating redox conditions. The mineralisation sequences documented at Sellafield are potentially promising in this context. Ferroan carbonate cements are sensitive indicators of later movement of oxidising ground waters. (author)

Research on near-surface disposal of very low level radioactive waste

International Nuclear Information System (INIS)

Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

2012-01-01

Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

Current R and D Status on High-Level Radioactive Waste Disposal in Selected Countries

Energy Technology Data Exchange (ETDEWEB)

Lee, Youn Myoung; Hwang, Yong Soo

2008-11-15

Current R and D status of such countries moving forward as the United States, Sweden, France, Japan and a few other countries for high-level radioactive waste (HLW) disposal in deep geological formation has been reviewed. Even though no HLW repositories have not practically constructed nor operated yet, lots of related R and D are being proceeded in many countries as well as in Korea. Through this brief review further progress is anticipated in this related R and D area in Korea.

Way of thinking and method of promotion of disposal of high level radioactive waste

International Nuclear Information System (INIS)

Toyota, Masatoshi

1993-01-01

It is decided that the high level waste separated from spent fuel is solidified with glass, stored for 30-50 years to cool it down, and the final disposal is done under the responsibility of the government. As to the final disposal of high level waste, the method of enclosing glass-solidified waste in robust containers and burying them in deep stable strata to isolate from human environment is considered to be the safest. The significance of fuel reprocessing is the proper and safe separation and control of high level waste besides the reuse of unburned uranium and newly formed plutonium in spent fuel. The features of the high level waste solids are that their amount to be generated is little, the radioactivity attenuates with the lapse of time, the heat generation decreases with the lapse of time, and they are hard to elute and move. In order to prevent radioactive substances from appearing in human environment by being dissolved in groundwater, those are isolated with the combination of natural and artificial barriers. The requirements for the barriers are discussed. The research and development are in progress on the establishment of stratum disposal technology, the evaluation of suitability of geological environment and the selection of expected disposal grounds. (K.I.)

FERRATE TREATMENT FOR REMOVING CHROMIUM FROM HIGH-LEVEL RADIOACTIVE TANK WASTE

International Nuclear Information System (INIS)

Sylvester, Paul; Rutherford, Andy; Gonzalez-Martin, Anuncia; Kim, J.; Rapko, Brian M.; Lumetta, Gregg J.

2000-01-01

A method has been developed for removing chromium from alkaline high-level radioactive tank waste. Removing chromium from these wastes is critical in reducing the volume of waste requiring expensive immobilization and deep geologic disposition. The method developed is based on the oxidation of insoluble chromium(III) compounds to soluble chromate using ferrate. The tests conducted with a simulated Hanford tank sludge indicate that the chromium removal with ferrate is more efficient at 5 M NaOH than at 3 M NaOH. Chromium removal increases with increasing Fe(VI)/Cr(III) molar ratio, but the chromium removal tends to level out for Fe(VI)/Cr(III) greater than 10. Increasing temperature leads to better chromium removal, but higher temperatures also led to more rapid ferrate decomposition. Tests with radioactive Hanford tank waste generally confirmed the simulant results. In all cases examined, ferrate enhanced the chromium removal, with a typical removal of around 60-70% of the total chromium present in the washed sludge solids. The ferrate leachate solutions did not contain significant concentrations of transuranic elements, so these solutions could be handled as low-activity waste

Geological setting of the Novi Han radioactive waste storage site

International Nuclear Information System (INIS)

Evstatiev, D.; Kozhukharov, D.

2000-01-01

The geo environment in the area of the only operating radioactive waste repository in Bulgaria has been analysed. The repository is intended for storage of all kinds of low and medium level radioactive wastes with the exception of these from nuclear power production. The performed investigations prove that the 30 years of operation have not caused pollution of the geo environment. Meanwhile the existing complex geological settings does not provide prerequisites to rely on the natural geological safety barriers. The studies performed so far are considered to be incomplete since they do not provide the necessary information for the development of a model describing the radionuclide migration as well as for understanding of the neotectonic circumstances. The tasks of the future activities are described in order to obtain more detailed information about the geology in the area. (authors)

Siting, design and construction of a deep geological repository for the disposal of high level and alpha bearing wastes

International Nuclear Information System (INIS)

1990-06-01

The main objective of this document is to summarize the basic principles and approaches to siting, design and construction of a deep geological repository for disposal of high level and alpha bearing radioactive wastes, as commonly agreed upon by Member States. This report is addressed to decision makers and technical managers as well as to specialists planning for siting, design and construction of geological repositories for disposal of high level and alpha bearing wastes. This document is intended to provide Member States of the IAEA with a summary outline for the responsible implementing organizations to use for siting, designing and constructing confinement systems for high level and alpha bearing radioactive waste in accordance with the protection objectives set by national regulating authorities or derived from safety fundamentals and standards of the IAEA. The protection objectives will be achieved by the isolation of the radionuclides from the environment by a repository system, which consists of a series of man made and natural safety barriers. Engineered barriers are used to enhance natural geological containment in a variety of ways. They must complement the natural barriers to provide adequate safety and necessary redundancy to the barrier system to ensure that safety standards are met. Because of the long timescales involved and the important role of the natural barrier formed by the host rock, the site selection process is a key activity in the repository design and development programme. The choice of the site, the investigation of its geological setting, the exploration of the regional hydrogeological setting and the primary underground excavations are all considered to be part of the siting process. 16 refs

Application of GIS in siting disposal repository for high level radioactive waste

International Nuclear Information System (INIS)

Zhong Xia; Wang Ju; Huang Shutao

2010-01-01

High level radioactive waste geo-disposal is directly related to environment protection and Sustainable Utilization of nuclear energy. To ensure both success and long-term safe disposal of the high level-radioactive waste, finding suitable sites is an important step in the research. Meanwhile, siting and evaluation the geo-disposal repository for high level-radioactive waste need a wide range of relevant information, including geology and geophysical surveys data, geochemistry data and other geoscience data in the field. At the same time, some of the data has its spatial property. Geographic information system (GIS) have a role to play in all geographic and spatial aspects of the development and management of the siting disposal repository. GIS has greatly enhanced our ability to store, analyze and communicate accounts of the information. This study was conducted to compare the more suitable sites for the repository using GIS -based on the data which belongs to the preselected area in BeiShan, Gansu Province, China. First, the data of the pre-selected site is captured by GIS and stored in the geoscience database. Then, according to the relevant guide line in the field, the analysis models based on GIS are build. There are some thematic layers of the sites character grouped into two basic type, namely social factors(town, traffic and nuclear plant) and natural factors (water, land and animals and plants).In the paper, a series of GIS models was developed to compare the pre-selected areas in order to make optimal decision. This study shows that with appropriate and enough information GIS used in modeling is a powerful tool for site selection for disposal repository. (authors)

Proposed classification scheme for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1986-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level (radioactive) waste (HLW) as (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel...that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission...determines...requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph B. The approach also results in definitions of other wastes classes, i.e., transuranic (TRU) and low-level waste (LLW). The basic waste classification scheme that results from the quantitative definitions of highly radioactive and requires permanent isolation is depicted. The concentrations of radionuclides that correspond to these two boundaries, and that may be used to classify radioactive wastes, are given

An assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Costello, J.M.

1982-10-01

The principles of management and disposal of highly radioactive wastes contained in spent fuel from nuclear power generation are described. The status of developments in spent fuel reprocessing, high-level waste solidificaton and geologic isolation is reviewed. Some generic studies on the possible range of annual radiological doses to individuals from waste repositories are discussed and compared with doses from some existing nuclear power and fuel cycle operations, and with the dose received annually from an average background of naturally occurring radiation

Modeling in low-level radioactive waste management from the US Geological Survey perspective

International Nuclear Information System (INIS)

Robertson, J.B.

1980-01-01

The United States Geological Survey (USGS) is a long-standing proponent of using models as tools in geohydrologic investigations. These models vary from maps and core samples to elaborate digital computer algorithms, depending on the needed application and resources available. Being a non-regulatory scientific agency, the USGS uses models primarily for: improving modeling technology, testing hypotheses, management of water resources, providing technical advice to other agencies, parameter sensitivity analysis, and determination of parameter values (inverse problems). At low-level radioactive waste disposal sites, we are most interested in developing better capabilities for understanding the groundwater flor regime within and away from burial trenches, geochemical factors affecting nuclide concentration and mobility in groundwater, and the effects that various changes in the geohydrologic conditions have on groundwater flow and nuclide migration. Although the Geological Survey has modeling capabilities in a variety of complex problems, significant deficiencies and limitations remain in certain areas, such as fracture flow conditions and solute transport in the unsaturated zone. However, even more serious are the deficiencies in measuring or estimating adequate input data for models and verification of model utility on real problems. Flow and transport models are being used by the USGS in several low-level disposal site studies, with varying degrees of sucess

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

Assessment of natural radioactivity levels in rocks and their relationships with the geological structure of Johor state, Malaysia.

Science.gov (United States)

Alnour, I A; Wagiran, H; Ibrahim, N; Hamzah, S; Elias, M S; Laili, Z; Omar, M

2014-01-01

The distribution of natural radionuclides ((238)U, (232)Th and (40)K) and their radiological hazard effect in rocks collected from the state of Johor, Malaysia were determined by gamma spectroscopy using a high-purity germanium detector. The highest values of (238)U, (232)Th and (40)K activity concentrations (67±6, 85±7 and 722±18 Bg kg(-1), respectively) were observed in the granite rock. The lowest concentrations of (238)U and (232)Th (2±0.1 Bq kg(-1) for (238)U and 2±0.1 Bq kg(-1) for (232)Th) were observed in gabbro rock. The lowest concentration of (40)K (45±2 Bq kg(-1)) was detected in sandstone. The radium equivalent activity concentrations for all rock samples investigated were lower than the internationally accepted value of 370 Bq kg(-1). The highest value of radium equivalent in the present study (239±17 Bq kg(-1)) was recorded in the area of granite belonging to an acid intrusive rock geological structure. The absorbed dose rate was found to range from 4 to 112 nGy h(-1). The effective dose ranged from 5 to 138 μSv h(-1). The internal and external hazard index values were given in results lower than unity. The purpose of this study is to provide information related to radioactivity background levels and the effects of radiation on residents in the study area under investigation. Moreover, the relationships between the radioactivity levels in the rocks within the geological structure of the studied area are discussed.

An underground research tunnel for the validation of high-level radioactive waste disposal concept

International Nuclear Information System (INIS)

Kwon, S.; Park, S. I.; Park, J. H.; Cho, W. J.; Han, P. S.

2005-01-01

In order to dispose of high-level radioactive waste(HLW) safely in geological formations, it is necessary to assess the feasibility, safety, appropriateness, and stability of the disposal concept at an underground research site, which is constructed in the same geological formation as the host rock. In this study, minimum requirements and the conceptual design for an efficient construction of a small scale URL, which is named URT, were derived based on a literature review. To confirm the validity of the conceptual design for construction at KAERI, a geological survey including a seismic refraction survey, electronic resistivity survey, borehole drilling, and in situ and laboratory tests were carried out. Based on the results, it was possible to design URT effectively with a consideration of the site characterization. The construction of URT was started in May 2005 and the first stage of the construction of the access tunnel could be successfully completed in Aug. 2005

Basic study on behaviors of radioactive and toxic inorganic elements in environment, and environmental assessment for geological disposal of high-level radioactive wastes. Outline of the prize-winning study of the 12th Osaka Nuclear Science Corporation Prize

Energy Technology Data Exchange (ETDEWEB)

Fujikawa, Yoko; Kudo, Akira [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.

1999-01-01

This study was made aiming to establish geological disposal technology for high-level radioactive wastes generated in nuclear power plant. A basic study for the technology was made using various radioactive materials containing Pu, U, Cs, Se, etc. as a tracer. First, adsorption mechanisms of various nuclides in ground water such as Cs, Co, Se, etc. onto rocks were investigated by indoor experiment. A certain correlation between the apparent adsorption rate of a nuclide onto rocks and diffusion coefficient into micropores in rocks was demonstrated both theoretically and experimentally. To estimate the radionuclide migration during more than one thousand years based on the results from indoor experiments is difficult, so that construction of a mathematical model was attempted to make numerical simulation. Thus,it was suggested that the properties of underground barrier are considerably related to the adsorption rates of nuclides and also diffusion coefficients into micropores. In addition, the effects of soil microorganisms and organic compounds on the behaviors of radioactive nuclides in soil ecosphere were investigated by extra-low level analysis of long-life radioactivities. More than 10% of Pu derived from Atomic Bomb at Nagasaki were found to be strongly bound to organic compounds in soils, showing that the element is extremely reactive with organic substances. (M.N.)

Admissible thermal loading in geological formations. Consequences on radioactive waste disposal methods

International Nuclear Information System (INIS)

1982-01-01

The thermal loading in salt formation is studied for the disposal of high-level radioactive waste embedded in glass. Temperature effect on glass leaching, stability of gel layer on glass surface, quantity of leaching solution available in the borehole and corrosion resistance of materials used for containers are examined. The geological storage medium must satisfy particularly complex requirements: stratigraphy, brine migration, permeability, fissuring, mechanical strength, creep, thermal expansion, cavity structure ..

A model for the analysis of a normal evolution scenarios for a deep geological granite repository for high-level radioactive waste

International Nuclear Information System (INIS)

Cormenzana Lopez, J.L.; Cunado, M.A.; Lopez, M.T.

1996-01-01

The methodology usually used to evaluate the behaviour of deep geological repositories for high-level radioactive wastes comprises three phases: Identification of factors (processes, characteristics and events) that can affect the repository. Generation of scenarios. In general, a normal evolution scenario (Reference Scenario) and various disruptive scenarios (earthquake, human intrusion, etc) are considered. Evaluation of the behaviour of the repository in each scenario. The normal evolution scenario taking into account all factors with a high probability of occurrence is the first to be analysed. The performance assessment of behaviour being carried out by ENRESA for the AGP Granite has led to the identification of 63 of these factors. To analyse repository behaviour in the normal evolution scenario, it is necessary to first of all create an integrated model of the global system. This is a qualitative model including the 63 factors identified. For a global view of a such a complex system, it is very useful to graphically display the relationship between factors in an Influence Diagram. This paper shows the Influence Diagram used in the analysis of the AGP Granite Reference Scenario. (Author)

Impacts of new developments in partitioning and transmutation on the disposal of high-level nuclear waste in a mined geologic repository

International Nuclear Information System (INIS)

Ramspott, L.D.; Jor-Shan Choi; Halsey, W.; Pasternak, A.; Cotton, T.; Burns, J.; McCabe, A.; Colglazier, W.; Lee, W.W.L.

1992-03-01

During the 1970s, the United States and other countries thoroughly evaluated the options for the safe and final disposal of high-level radioactive wastes (HLW). The worldwide scientific community concluded that deep geologic disposal was clearly the most technically feasible alternative. They also ranked the partitioning and transmutation (P-T) of radionuclides among the least favored options. A 1982 report by the International Atomic Energy Agency summarized the key reasons for that ranking: ''Since the long-term hazards are already low, there is little incentive to reduce them further by P-T. Indeed the incremental costs of introducing P-T appear to be unduly high in relation to the prospective benefits.'' Recently, the delays encountered by the US geologic disposal program for HLW, along with advanced in the development of P-T concepts, have led some to propose P-T as a means of reducing the long-term risks from the radioactive wastes that require disposal and thus making it easier to site, license, and build a geologic repository. This study examines and evaluates the effects that introducing P-T would have on the US geologic disposal program

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

Elicitation and use of expert judgment in performance assessment for high-level radioactive waste repositories

International Nuclear Information System (INIS)

Bonano, E.J.; Hora, S.C.; Keeney, R.L.; von Winterfeldt, D.

1990-05-01

This report presents the concept of formalizing the elicitation and use of expert judgment in the performance assessment of high-level radioactive waste (HLW) repositories in deep geologic formations. The report begins with a discussion of characteristics (advantages and disadvantages) of formalizing expert judgment examples of previous uses of expert judgment in radioactive waste programs, criteria that can assist in deciding when to formalize expert judgment, and the relationship of formal use of expert judgment to data collection and modeling. The current state of the art with respect to the elicitation, use, and communication of formal expert judgment is presented. The report concludes with a discussion on potential applications of formal expert judgment in performance assessment of HLW repositories. 93 refs

Self-sealing of rock fractures. A possibility around the repositories of high-level radioactive wastes

International Nuclear Information System (INIS)

Chigira, Masahiro; Nakata, Eiji

1995-01-01

To the goal of the safe geological disposal of high-level radioactive wastes (HLW), we must provide long-term confidence for the isolation of HLW in various ways. In particular, groundwater flow, the most likely transport media of radioactive nuclides from HLW, must be restricted around a repository for long time. For that purpose, grouting techniques using cement, bentonite, or other materials have been studied in many countries. In this paper we report the results of a series of experiments on silica precipitation behavior in a flow path with negative temperature gradients in granite and also describe a natural example of hydrothermal alteration of diatomite intruded by andesite. Based on these, we will discuss the possibility of self-sealing around HLW repository. (J.P.N.)

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for trivalent actinoids and samarium

International Nuclear Information System (INIS)

Kitamura, Akira; Fujiwara, Kenso; Yui, Mikazu

2010-01-01

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of trivalent actinoids (actinium(III), plutonium(III), americium(III) and curium(III)) and samarium(III) was carried out. Refinement of thermodynamic data for these elements was based on the thermodynamic database for americium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Based on the similarity of chemical properties among trivalent actinoids and samarium, complementary thermodynamic data for their species expected under the geological disposal conditions were selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

Geologic and hydrologic characterization and evaluation of the Basin and Range Province relative to the disposal of high-level radioactive waste: Part I, Introduction and guidelines

Science.gov (United States)

Bedinger, M.S.; Sargent, Kenneth A.; Reed, J.E.

1984-01-01

used in characterizing the Province.The current (1983) needs for a high-level radioactive waste repository include: (1) Disposal in a mined repository; (2) retrievability of the waste for as much as 50 years; and (3) confidence of isolation of the waste from the accessible environment. Isolation of the waste needs to be assured using geologic and hydrologic conditions that: (1) Minimize risk of inadvertent future intrusions by man; (2) minimize the possibility of disturbance by processes that would expose the waste or increase its mobility; and (3) provide a system of natural barriers to the migration of waste by ground water. The guidelines adopted by the Province Working Group are designed to provide a standard with which these conditions can be compared.The guidelines can be grouped into four principal categories: (1) Potential host media, (2) ground-water conditions, (3) tectonic conditions, and. (4) occurrence of natural resources. Ideally the host medium constitutes the first natural barrier to migration of radionculides. The host medium ideally should be a rock type that prevents or retards dissolution and transport of radionuclides. Rocks in both the saturated and unsaturated zones may have desirable characteristics for host media. Rocks-other than the host-in the ground-water flow path from the repository ideally should be major barriers to radionuclide migration. Confining beds of low permeability might be present to retard the rate of flow between more permeable beds. Additionally, sorption of radionuclides by materials such as clays and zeolites in the flow path can further retard the flow of radionuclides by several orders of magnitude. Tectonic conditions in an area should not present a probable cause for exhumation or increased mobility of radioactive waste. Natural resources are a factor for consideration because of the problem of future human intrusion and exposure to radioactivity in the quest for minerals, oil, gas, water, and geothermal resources

Ferrate treatment for removing chromium from high-level radioactive tank waste.

Science.gov (United States)

Sylvester, P; Rutherford, L A; Gonzalez-Martin, A; Kim, J; Rapko, B M; Lumetta, G J

2001-01-01

A method has been developed for removing chromium from alkaline high-level radioactive tank waste. Removing chromium from these wastes is critical in reducing the volume of waste requiring expensive immobilization and deep geologic disposition. The method developed is based on the oxidation of insoluble chromium(III) compounds to soluble chromate using ferrate. This method could be generally applicable to removing chromium from chromium-contaminated solids, when coupled with a subsequent reduction of the separated chromate back to chromium(III). The tests conducted with a simulated Hanford tank sludge indicate that the chromium removal with ferrate is more efficient at 5 M NaOH than at 3 M NaOH. Chromium removal increases with increasing Fe(VI)/Cr(II) molar ratio, but the chromium removal tends to level out for Fe(VI)/ Cr(III) greaterthan 10. Increasingtemperature leadsto better chromium removal, but higher temperatures also led to more rapid ferrate decomposition. Tests with radioactive Hanford tank waste generally confirmed the simulant results. In all cases examined, ferrate enhanced the chromium removal, with a typical removal of around 60-70% of the total chromium present in the washed sludge solids. The ferrate leachate solutions did not contain significant concentrations of transuranic elements, so these solutions could be disposed as low-activity waste.

Proposed classification scheme for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1986-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level radioactive waste (HLW) as: (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel....that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission....determines....requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph (B). The approach also results in definitions of other waste classes, i.e., transuranic (TRU) and low-level waste (LLW). A basic waste classification scheme results from the quantitative definitions

Underground disposal of vitrified high level radioactive waste: a review of research and development

International Nuclear Information System (INIS)

1982-11-01

A review has been undertaken of the worldwide status of research and development related to the geological disposal of vitrified high level radioactive waste. The nature and quantities of vitrified high level waste that will arise from nuclear power generation in the UK have been estimated and considered. The safety case for establishing a geological repository would have to be based on predictive models, which could adequately represent the interactions and effects of a wide range of gradual processes and possible sudden events. No detailed repository design has yet been published, but the configuration currently favoured, in the UK and in most other countries, comprises a small number of vertical shafts, from which a network of horizontal tunnels would be excavated. Waste packages would be placed in holes drilled in the floors of the tunnels. The excavation of such a repository in hard crystalline rock, in a thick homogeneous formation of rock salt, or in the less plastic argillaceous formations, appears to be within the scope of present technology. Rock types available in the UK, which are likely to prove suitable for the accommodation of a repository, have been identified. The strategies and programmes for high level waste disposal in other countries have been reviewed. (U.K.)

Feasibility of disposal of high-level radioactive waste into the seabed. Volume 2: Radiological assessment

International Nuclear Information System (INIS)

Marsily, G. de; Berhendt, V.; Ensminger, D.; Flebus, C.; Hutchinson, B.; Kane, P.; Karpf, A.; Klett, R.; Mobbs, S.; Poulin, M.; Stanner, D.

1988-01-01

One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This report presents the results of the radiological assessment which consists in estimating the detriment to man and to the environment which could result from the disposal of high level nuclear waste within seabed sediments in the deep oceans

Disposal of high-level radioactive wastes in the unsaturated zone: technical considerations and response to comments. Final report

International Nuclear Information System (INIS)

Hackbarth, C.J.; Nicholson, T.J.; Evans, D.D.

1985-10-01

On July 22, 1985, the US Nuclear Regulatory Commission (NRC) promulgated amendments to 10 CFR Part 60 concerning disposal of high-level radioactive waste (HLW) in geologic repositories in the unsaturated zone (50 FR 29641). This report contains a discussion of the principal technical issues considered by the NRC staff during the development of these amendments. It expands or revises certain technical discussions originally presented in draft NUREG-1046 (February 1984) based on public comment letters and an increasing understanding of the physical, geochemical, and hydrogeologic processes operative in unsaturated geologic media. The following issues related to disposal of HLW within the unsaturated zone are discussed: hydrogeologic properties and conditions, heat dissipation and temperature, geochemisty, retrievability, potential for exhumation of the radioactive waste by natural causes and by human intrusion, the effects of future climatic changes on the level of the regional water table, and transport of radionuclides in the gaseous state. The changes to 10 CFR Part 60 in definitions, siting criteria, and design criteria for the geologic repository operations area are discussed. Other criteria examined by the NRC staff but which were not changed in rule are the minimum 300-meter depth for waste emplacement, limitations on exploratory boreholes, backfill requirements, waste package design criteria, and provisions for ventilation

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.)

FEBEX project: full-scale engineered barriers experiment for a deep geological repository for high level radioactive waste in crystalline host rock. Final report

International Nuclear Information System (INIS)

Alberdi, J.; Barcala, J. M.; Campos, R.; Cuevas, A. M.; Fernandez, E.

2000-01-01

FEBEX has the multiple objective of demonstrating the feasibility of manufacturing, handling and constructing the engineered barriers and of developing codes for the thermo-hydro-mechanical and thermo-hydro-geochemical performance assessment of a deep geological repository for high level radioactive wastes. These objectives require integrated theoretical and experimental development work. The experimental work consists of three parts: an in situ test, a mock-up test and a series of laboratory tests. The experiments is based on the Spanish reference concept for crystalline rock, in which the waste capsules are placed horizontally in drifts surround by high density compacted bentonite blocks. In the two large-scale tests, the thermal effects of the wastes were simulated by means of heaters; hydration was natural in the in situ test and controlled in the mock-up test. The large-scale tests, with their monitoring systems, have been in operation for more than two years. the demonstration has been achieved in the in situ test and there are great expectation that numerical models sufficiently validated for the near-field performance assessment will be achieved. (Author)

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.

Glasses used for the high level radioactive wastes storage

International Nuclear Information System (INIS)

Sombret, C.

1983-06-01

High level radioactive wastes generated by the reprocessing of spent fuels is an important concern in the conditioning of radioactive wastes. This paper deals with the status of the knowledge about glasses used for the treatment of these liquids [fr

The State of the Art of the Borehole Disposal Concept for High Level Radioactive Waste

International Nuclear Information System (INIS)

Ji, Sung Hoon; Koh, Yong Kwon; Choi, Jong Won

2012-01-01

As an alternative of the high-level radioactive waste disposal in the subsurface repository, a deep borehole disposal is reviewed by several nuclear advanced countries. In this study, the state of the art on the borehole disposal researches was reviewed, and the possibility of borehole disposal in Korean peninsula was discussed. In the deep borehole disposal concept radioactive waste is disposed at the section of 3 - 5 km depth in a deep borehole, and it has known that it has advantages in performance and cost due to the layered structure of deep groundwater and small surface disposal facility. The results show that it is necessary to acquisite data on deep geologic conditions of Korean peninsula, and to research the engineering barrier system, numerical modeling tools and disposal techniques for deep borehole disposal.

Assessment of studies and researches on warehousing - High-level and intermediate-level-long-lived radioactive wastes - December 2012

International Nuclear Information System (INIS)

2013-01-01

This large report first presents the approach adopted for the study and research on the warehousing of high-level and intermediate-level-long-lived radioactive wastes. It outlines how reversible storage and warehousing are complementary, discusses the lessons learned from researches performed by the CEA on long duration warehousing, presents the framework of studies and researches performed since 2006, and presents the scientific and technical content of studies and researches (warehousing need analysis, search for technical options providing complementarity with storage, extension or creation of warehousing installations). The second part addresses high-level and intermediate-level-long-lived radioactive waste parcels, indicates their origins and quantities. The third part proposes an analysis of warehousing capacities: existing capacities, French industrial experience in waste parcel warehousing, foreign experience in waste warehousing. The fourth part addresses reversible storage in deep geological formation: storage safety functions, storage reversibility, storage parcels, storage architecture, chronicle draft. The fifth part proposes an inventory of warehousing needs in terms of additional capacities for the both types of wastes (high-level, and intermediate-level-long-lived), and discusses warehousing functionalities and safety objectives. The sixth and seventh parts propose a detailed overview of design options for warehousing installations, respectively for high-level and for intermediate-level-long-lived waste parcels: main technical issues, feasibility studies of different concepts or architecture shapes, results of previous studies and introduction to studies performed since 2011, possible evolutions of the HA1, HA2 and MAVL concepts. The eighth chapter reports a phenomenological analysis of warehousing and the optimisation of material selection and construction arrangements. The last part discusses the application of researches to the extension of the

Necessary contents of public outreach for high level radioactive waste disposal

International Nuclear Information System (INIS)

Kanzaki, Noriko; Okamoto, Koji

2011-01-01

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

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

In situ-experiments on the disposal of high-level radioactive wastes (HAW) at the Asse salt mine Federal Republic of Germany

International Nuclear Information System (INIS)

Kuhn, K.; Rothfuchs, T.

1989-01-01

Deep geological salt formations are considered as being the most suitable medium for the disposal of radioactive wastes in the Federal Republic of Germany (FRG). This paper reports how, in order to develop and to prove the necessary disposal techniques, the Asse Salt Mine in the northern part of Germany is being used as a national R and D facility for the execution of representative in situ-tests. Besides the test-wise disposal of low-and medium-level radioactive waste, a series of in situ experiments was performed on the disposal of high-level radioactive waste (HAW). The so-called HAW repository is being performed from 1983 through 1994 will be the most important pilot test for the HAW repository in the FRG. During this experiment, 30 vitrified high-level radioactive heat and radiation sources will be emplaced in six underground boreholes. The duration of testing will be approximately five years. In addition to the investigations of the interactions of the heat and radiation sources and the host rock, a complete handling system for HAW-canisters is being developed and proved

Radioactive waste disposal programme and siting regions for geological deep repositories. Executive summary. November 2008; Entsorgungsprogramm und Standortgebiete fuer geologische Tiefenlager. Zusammenfassung. November 2008

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-11-15

There are radioactive wastes in Switzerland. Since many decades they are produced by the operation of the five nuclear power plants, by medicine, industry and research. Important steps towards the disposal of these wastes are already realized; the corresponding activities are practised. This particularly concerns handling and packaging of the radioactive wastes, their characterization and inventory, as well as the interim storage and the inferred transportations. Preparatory works in the field of scientific research on deep geological repositories have allowed to acquire high level of technical and scientific expertise in that domain. The feasibility of building long-term safe geological repositories in Switzerland was demonstrated for all types of radioactive wastes; the demonstration was accepted by the Federal Council. There is enough knowledge to propose geological siting regions for further works. The financial funds already accumulated guaranty the financing of the dismantling of the power plants as well as building deep geological repositories for the radioactive wastes. The regulations already exist and the organisational arrangements necessary for the fruitful continuation of the works already done have been taken. The programme of the disposal of radioactive wastes also describes the next stages towards the timely realization of the deep repositories as well as the level of the financial needs. The programme is updated every five years, checked by the regulatory bodies and accepted by the Federal Council who reports to the parliament. The process of choosing a site, which will be completed in the next years, is detailed in the conceptual part of the programme for deep geological repositories. The NAGRA proposals are based exclusively on technical and scientific considerations; the global evaluation taking into account also political considerations has to be performed by the authorities and the Federal Council. The programme states that at the beginning of

Material chemistry challenges in vitrification of high level radioactive waste

International Nuclear Information System (INIS)

Kaushik, C.P.

2008-01-01

Full text: Nuclear technology with an affective environmental management plan and focused attention on safety measures is a much cleaner source of electricity generation as compared to other sources. With this perspective, India has undertaken nuclear energy program to share substantial part of future need of power. Safe containment and isolation of nuclear waste from human environment is an indispensable part of this programme. Majority of radioactivity in the entire nuclear fuel cycle is high level radioactive liquid waste (HLW), which is getting generated during reprocessing of spent nuclear fuels. A three stage strategy for management of HLW has been adopted in India. This involves (i) immobilization of waste oxides in stable and inert solid matrices, (ii) interim retrievable storage of the conditioned waste product under continuous cooling and (iii) disposal in deep geological formation. Borosilicate glass matrix has been adopted in India for immobilization of HLW. Material issue are very important during the entire process of waste immobilization. Performance of the materials used in nuclear waste management determines its safety/hazards. Material chemistry therefore has a significant bearing on immobilization science and its technological development for management of HLW. The choice of suitable waste form to deploy for nuclear waste immobilization is difficult decision and the durability of the conditioned product is not the sole criterion. In any immobilization process, where radioactive materials are involved, the process and operational conditions play an important role in final selection of a suitable glass formulation. In remotely operated vitrification process, study of chemistry of materials like glass, melter, materials of construction of other equipment under high temperature and hostile corrosive condition assume significance for safe and un-interrupted vitrification of radioactive to ensure its isolation waste from human environment. The present

Feasibility of disposal of high-level radioactive waste into the seabed. Volume 3: Geoscience characterization studies

International Nuclear Information System (INIS)

Shephard, L.E.; Auffret, G.A.; Buckley, D.E.; Schuettenhelm, R.T.E.; Searle, R.C.

1988-01-01

One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This report summarizes the results of a study performed to establish if, on the basis of available data, sites may be found that will satisfy the geoscience requirements for a potential subseabed high-level waste repository

Process for final storage of high level radioactive fission product solution

International Nuclear Information System (INIS)

Ellis, J.R.B.; Fries, B.A.

1984-01-01

In this process for the storage of an aqueous solution of radioactive nuclides, the solution is diluted with system water, which is obtained from a reservoir below the bottom of the sea in a porous geological stratum. After dilution, the diluted solution is injected into the same geological stratum under the bottom of the sea. (orig.) [de

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

1985-03-01

This report presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste. It represents a major update and expansion of the Analysis presented to Congress in our summary report, Managing Commercial High-Level Radioactive Waste, published in April of 1982 (NWPA). This new report is intended to contribute to the implementation of NWPA, and in particular to Congressional review of three major documents that DOE will submit to the 99th Congress: a Mission Plan for the waste management program; a monitored retrievable storage (MRS) proposal; and a report on mechanisms for financing and managing the waste program. The assessment was originally focused on the ocean disposal of nuclear waste. OTA later broadened the study to include all aspects of high-level waste disposal. The major findings of the original analysis were published in OTA's 1982 summary report

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)

Michigan high-level radioactive waste program. Technical progress report for 1985

International Nuclear Information System (INIS)

1986-01-01

In 1985, five crystalline rock formations located in Michigan's Upper Peninsula were under consideration in the regional phase of the Department of Energy's (DOE) search for the site of the nation's second high-level radioactive waste repository. The Michigan Department of Public Health has been designated by the Governor as lead state agency in matters related to high-level radioactive waste (HLRW). Mr. Lee E. Jager, Chief of the Department's Bureau of Environmental and Occupational Health, has been designated as the state contact person in this matter, and the Bureau's Division of Radiological Health, Office of Radioactive Waste Management (ORWM), has been designated to provide staff support. Recognizing that adequate state involvement in the various aspects of the Federal high-level radioactive waste (HLRW) programs would require a range of expertise beyond the scope of any single state agency, Governor Blanchard established the High-Level Radioactive Waste Task Force in 1983. In support of the Task Force efforts concerning the implementation of its change, the Department negotiated and concluded an agreement with the DOE, under which federal funds are provided to support state HLRW activities. This report outlines state activities for the calendar year 1985, funded under that agreement

The geology of some United Kingdom nuclear sites related to the disposal of low and medium level radioactive wastes

International Nuclear Information System (INIS)

Robins, N.S.

1980-04-01

The geological sequences beneath ten British nuclear sites are extrapolated from the available data. Formations that are potentially suitable hosts for low and medium level radioactive waste are identified and their relative merits assessed. Of the sites investigated, formations beneath five afford little or no potential, formations beneath a further three offer only moderate potential and sites underlain by the most favourable formations are at Dounreay and Harwell. (author)

The geology of some United Kingdom nuclear sites related to the disposal of low and medium level radioactive wastes

International Nuclear Information System (INIS)

Robins, N.S.

1980-06-01

The geological sequences beneath a further twelve nuclear sites in Britain are predicted from available data. Formations that are potentially suitable hosts for low and medium-level radioactive waste are identified and their relative merits assessed. Of the sites investigated, formations beneath six afford little or no potential, formations beneath a further 4 offer only moderate potential and sites underlain by the most favourable formations are Dungeness and Hinkley Point. (author)

A proposed classification system for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1987-06-01

This report presents a proposal for quantitative and generally applicable risk-based definitions of high-level and other radioactive wastes. On the basis of historical descriptions and definitions of high-level waste (HLW), in which HLW has been defined in terms of its source as waste from reprocessing of spent nuclear fuel, we propose a more general definition based on the concept that HLW has two distinct attributes: HLW is (1) highly radioactive and (2) requires permanent isolation. This concept leads to a two-dimensional waste classification system in which one axis, related to ''requires permanent isolation,'' is associated with long-term risks from waste disposal and the other axis, related to ''highly radioactive,'' is associated with shorter-term risks due to high levels of decay heat and external radiation. We define wastes that require permanent isolation as wastes with concentrations of radionuclides exceeding the Class-C limits that are generally acceptable for near-surface land disposal, as specified in the US Nuclear Regulatory Commission's rulemaking 10 CFR Part 61 and its supporting documentation. HLW then is waste requiring permanent isolation that also is highly radioactive, and we define ''highly radioactive'' as a decay heat (power density) in the waste greater than 50 W/m 3 or an external radiation dose rate at a distance of 1 m from the waste greater than 100 rem/h (1 Sv/h), whichever is the more restrictive. This proposal also results in a definition of Transuranic (TRU) Waste and Equivalent as waste that requires permanent isolation but is not highly radioactive and a definition of low-level waste (LLW) as waste that does not require permanent isolation without regard to whether or not it is highly radioactive

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

High-level radioactive wastes. Supplement 1

International Nuclear Information System (INIS)

McLaren, L.H.

1984-09-01

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations

Operation of the online forum for the discussion of high level radioactive waste and related issues

International Nuclear Information System (INIS)

Furihata, Shiori; Sugiyama, Naoki; Kikuchi, AKiko; Takizawa, Masayuki

2002-03-01

JNC is releasing information on the technical reliability for geological disposal of high-level radioactive waste (HLW) to public. However, the recognition and understanding of general public on the geological disposal of HLW are not satisfied. Recently more and more people are using the Internet, which is two-way, instant and open communication network. So JNC has offered the opportunity for discussing the topics related to geological disposal of HLW on the Internet web site since fiscal year 1999. In this fiscal year, the online forum was opened from January 25 to March 11. The forum was held on the web server independent from JNC so that discussion is done as fairly and objectively as possible. The event, which is the online discussion by university students in nation-wide, was specially held. The number of accesses to the forum significantly increased in this period compared to that of last two fiscal years. The adequate operation of the forum and the presentation of the information about geological disposal of HLW were surveyed by the questionnaire distributed to the participants. (author)

Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings

Science.gov (United States)

Bedinger, Marion S.; Stevens, Peter R.

1990-01-01

In the United States, low-level radioactive waste is disposed by shallow-land burial. Low-level radioactive waste generated by non-Federal facilities has been buried at six commercially operated sites; low-level radioactive waste generated by Federal facilities has been buried at eight major and several minor Federally operated sites (fig. 1). Generally, low-level radioactive waste is somewhat imprecisely defined as waste that does not fit the definition of high-level radioactive waste and does not exceed 100 nCi/g in the concentration of transuranic elements. Most low-level radioactive waste generated by non-Federal facilities is generated at nuclear powerplants; the remainder is generated primarily at research laboratories, hospitals, industrial facilities, and universities. On the basis of half lives and concentrations of radionuclides in low-level radioactive waste, the hazard associated with burial of such waste generally lasts for about 500 years. Studies made at several of the commercially and Federally operated low-level radioactive-waste repository sites indicate that some of these sites have not provided containment of waste nor the expected protection of the environment.

Identification and understanding the factors affecting the public and political acceptance of long term storage of spent fuel and high-level radioactive wastes

International Nuclear Information System (INIS)

Gorea, Valica

2006-01-01

, during the storage. There is a powerful scientific and technical consensus according to which a well placed final repository must be provided with some barriers, including the geological and engineered ones. The wide-spread and accepted concept of final repository for spent fuel and high level waste is the so-called geological disposal which means the solid radioactive waste storage in underground repositories in a stable geological structure (ordinary at some hundreds of meters deep) so ensuring the isolation of radionuclides from biosphere on long term. The types of radioactive waste (high level and long life waste) which will be placed in geological repository are established by the national strategy and politics for the safe management of the radioactive waste. The development and implementation process of a repository can be achieved in the next non compulsory steps: - Developing the national politics in the field of safe management of the radioactive waste - Developing the legislative and institutional framework - Developing the technical concept of geological repository - Initiation of underground and surface investigations for the characterization of the host rock - Selecting the suitable site for an underground repository - Design, licensing for construction (which takes into account the environmental impact, nuclear safety and so on), operation and shut down. The decision to construct a geological repository must be taken by the Government or by the producers of waste. The steps for the establishing the legal framework, regulation and licensing are prerogatives of the Government, all the others steps could be achieved by non governmental organizations. The achievement of a geological repository, from the technical concept to the operation may last even more than 50 years and its operation some hundreds years. The paper contains the following sections: 1. Introduction; 2. Public and political acceptance; 3. Factors which affect the public and political

Geological storage of radioactive waste

International Nuclear Information System (INIS)

Barthoux, A.

1983-01-01

Certain radioactive waste contains substances which present, although they disappear naturally in a progressive manner, a potential risk which can last for very long periods, of over thousands of years. To ensure a safe long-term handling, provision has been made to bury it deep in stable geological structures which will secure its confinement. Radioactive waste is treated and conditioned to make it insoluble and is then encased in matrices which are to immobilize them. The most radioactive waste is thus incorporated in a matrix of glass which will ensure the insulation of the radioactive substances during the first thousands of years. Beyond that time, the safety will be ensured by the properties of the storage site which must be selected from now on. Various hydrogeological configurations have been identified. They must undergo detailed investigations, including even the creation of an underground laboratory. This document also presents examples of underground storage installations which are due to be built [fr

Measurement of gross beta radioactivity in high-level liquid waste

International Nuclear Information System (INIS)

Lu Feng; Lin Cansheng; Zhang Xianzi; Chen Guoan; Zhang Chonghai

1992-01-01

Using beta plastic scintillation counter of low level background, gross beta radioactivity of twelve samples for high-level liquid waste is determined directly. Beta efficiency curves of plastic scintillation counter for four mass thickness are calibrated in advance. Determining gross beta radioactivity, gross efficiency of the scintillation counter for various energy beta ray is calculated via weighted mean method with the ratio of radioactivity for each nuclide. The ratio of radioactivity for nuclides which have gamma disintegration is determined in terms of the radioactivity measured by gamma spectrometer. The ratio of the radioactivity for 90 Sr which has purity beta disintegration is calculated in terms of half life time approximation. The ratio of the radioactivity for 147 Pm which also has purity disintegration is calculated by means of apparent cooling-time approximation. The uncertainty of results for the present work is about +-15%

An analysis of the technical status of high level radioactive waste and spent fuel management systems

Science.gov (United States)

English, T.; Miller, C.; Bullard, E.; Campbell, R.; Chockie, A.; Divita, E.; Douthitt, C.; Edelson, E.; Lees, L.

1977-01-01

The technical status of the old U.S. mailine program for high level radioactive nuclear waste management, and the newly-developing program for disposal of unreprocessed spent fuel was assessed. The method of long term containment for both of these waste forms is considered to be deep geologic isolation in bedded salt. Each major component of both waste management systems is analyzed in terms of its scientific feasibility, technical achievability and engineering achievability. The resulting matrix leads to a systematic identification of major unresolved technical or scientific questions and/or gaps in these programs.

Geological disposal of high-level radioactive waste. Conceptual repository design in hard rock

International Nuclear Information System (INIS)

Beale, H.; Griffin, J.R.; Davies, J.W.; Burton, W.R.

1980-01-01

The paper gives an interim report on UK studies on possible designs for a repository for vitrified high-level radioactive waste in crystalline rock. The properties of the waste are described and general technical considerations of consequences of disposal in the rock. As an illustration, two basic designs are described associated with pre-cooling in an intermediate store. Firstly, a 'wet repository' is outlined wherein canisters are sealed up closely in boreholes in the rock in regions of low groundwater movement. Secondly, a 'dry repository' above sea level is described where emplacement in tunnels is followed by a loose backfill containing activity absorbers. A connection to deep permeable strata maintains water levels below emplacement positions. Variants on the two basic schemes (tunnel emplacement in a wet repository and in situ cooling) are also assessed. It is concluded that all designs discussed produce a size of repository feasible for construction in the UK. Further, (1) a working figure of 100 0 C per maximum rock temperature is not exceeded, (2) no insuperable engineering problems have so far been found, though rock mechanics studies are at an early stage; (3) it is not possible to discount the escape of a few long-lived 'man-made' isotopes. A minute increment to natural activity in the biosphere may occur from traces of uranium and its decay chains; (4) at this stage, all the designs are still possible candidates for the construction of a UK repository. (author)

High-level radioactive wastes. Supplement 1

Energy Technology Data Exchange (ETDEWEB)

McLaren, L.H. (ed.)

1984-09-01

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

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)

Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

International Nuclear Information System (INIS)

Moriyama, Yoshinori

1998-01-01

Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

Processing vessel for high level radioactive wastes

International Nuclear Information System (INIS)

Maekawa, Hiromichi

1998-01-01

Upon transferring an overpack having canisters containing high level radioactive wastes sealed therein and burying it into an underground processing hole, an outer shell vessel comprising a steel plate to be fit and contained in the processing hole is formed. A bury-back layer made of dug earth and sand which had been discharged upon forming the processing hole is formed on the inner circumferential wall of the outer shell vessel. A buffer layer having a predetermined thickness is formed on the inner side of the bury-back layer, and the overpack is contained in the hollow portion surrounded by the layer. The opened upper portion of the hollow portion is covered with the buffer layer and the bury-back layer. Since the processing vessel having a shielding performance previously formed on the ground, the state of packing can be observed. In addition, since an operator can directly operates upon transportation and burying of the high level radioactive wastes, remote control is no more necessary. (T.M.)

U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1983, 1984, and 1985

Science.gov (United States)

Dinwiddie, G.A.; Trask, N.J.

1986-01-01

The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research is described according to whether it is related most directly to: (1) high-level and transuranic wastes, (2) low-level wastes, or (3) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, and to studies of regions or environments where waste-disposal sites might be located. A significant part of the activity is concerned with techniques and methods for characterizing disposal sites and studies of geologic and hydrologic processes related to the transport and (or) retention of waste radionuclides.

Low- and intermediate level radioactive waste from Risoe, Denmark. Location studies for potential disposal areas. Report no. 3. Geological setting and tectonic framework in Denmark

Energy Technology Data Exchange (ETDEWEB)

Schack Pedersen, S.A.; Gravesen, P.

2011-07-01

The low and intermediate level radioactive waste from Risoe (the nuclear reactor buildings plus different types of material from the research periods) and radioactive waste from hospitals and research institutes have to be stored in a final disposal in Denmark for at least 300 years. The Minister for Health and Prevention presented the background and decision plan for the Danish Parliament in January 2009. All political parties agreed on the plan. The task for the Geological Survey of Denmark and Greenland (GEUS) is to find approximately 20 areas potentially useful for a waste disposal. These 20 areas are afterwards reduced to 2-3 most optimal locations. At these 2-3 locations, detailed field investigations of the geological, hydrogeological - hydrochemical and technical conditions will be performed. This report provides an introduction to the geological setting of Denmark with the focus on providing an overview of the distribution of various tectonic and structural features. These are considered important in the context of choosing suitable areas for the location of a disposal for radioactive waste. The geological structures, deep and shallow are important for the selection of potential disposals basically because the structures describes the geometry of the areas. Additionally, the structures provides the information about the risk of unwanted movements of the geological layers around the disposal that have to be investigated and evaluated as a part of the selection process. (LN)

Low- and intermediate level radioactive waste from Risoe, Denmark. Location studies for potential disposal areas. Report no. 3. Geological setting and tectonic framework in Denmark

International Nuclear Information System (INIS)

Schack Pedersen, S.A.; Gravesen, P.

2011-01-01

The low and intermediate level radioactive waste from Risoe (the nuclear reactor buildings plus different types of material from the research periods) and radioactive waste from hospitals and research institutes have to be stored in a final disposal in Denmark for at least 300 years. The Minister for Health and Prevention presented the background and decision plan for the Danish Parliament in January 2009. All political parties agreed on the plan. The task for the Geological Survey of Denmark and Greenland (GEUS) is to find approximately 20 areas potentially useful for a waste disposal. These 20 areas are afterwards reduced to 2-3 most optimal locations. At these 2-3 locations, detailed field investigations of the geological, hydrogeological - hydrochemical and technical conditions will be performed. This report provides an introduction to the geological setting of Denmark with the focus on providing an overview of the distribution of various tectonic and structural features. These are considered important in the context of choosing suitable areas for the location of a disposal for radioactive waste. The geological structures, deep and shallow are important for the selection of potential disposals basically because the structures describes the geometry of the areas. Additionally, the structures provides the information about the risk of unwanted movements of the geological layers around the disposal that have to be investigated and evaluated as a part of the selection process. (LN)

Problems of solidificated radioactive wastes burial into deep geological structures

International Nuclear Information System (INIS)

Kedrovskij, O.L.; Leonov, E.A.; Romadin, N.M.; Shishcits, I.Yu.

1981-01-01

Perspectives are noted of the radioactive wastes burial into deep geopogical structures. For these purposes it has been proposed to investigate severap types of rocks, which do not have intensive gas-generation when beeng heated; salt deposits and clays. Basing on the results of calculations it has been shown that the dimentions of zones of substantial deformations in the case of the high-level radioactive wastes burial to not exceed several hundreds of meters. Conclusion is made that in the case of choosing the proper geotogicat structure for burial and ir the case of inclusion in the structure of the burial site a zone of sanitary alienation, it is possible to isolate wastes safely for all the period of preservation. Preliminary demands have been formulated to geological structures and underground burial sites. As main tasks for optimizatiop of burial sited are considered: determination of necessary types, number and reliability of barriers which ensure isolation of wastes; to make prognoses of the stressed and deformed state of a geological massif on the influence of thermal field; investigation in changes of chemical and physical properties of rocks under heat, radiative and chemical influence; estimation of possible diffusion of radioactivity in a mountin massif; development of a rational mining-thechnological schemes of the burual of wastes of different types. A row of tasks in the farmeworks of this probtem are sotved successfutty. Some resutts are given of the theoretical investigations in determination of zones of distructions of rocks because of heat-load [ru

Development of grouting technologies for geological disposal of high level waste in Japan (1). Overall program and application of developed technologies

International Nuclear Information System (INIS)

Fujita, Tomoo; Sasamoto, Hiroshi; Sugita, Yutaka; Matsui, Hiroya

2013-01-01

The Japan Atomic Energy Agency started a grout project for geological disposal of high-level radioactive waste (HLW) in 2007. The aim of the project was to develop new grouting technologies and grout materials and also to develop models for performance assessments, prediction of the long-term radionuclide migration and identify detrimental changes in the host rock by the grout material leachate. This study presents the overall program and the application of key engineering technologies to the construction and operation of an underground facility for the geological disposal of HLW, with particular emphasis on the long-term effects of grout materials. (author)

Progress on the national low level radioactive waste repository and national intermediate level waste store

International Nuclear Information System (INIS)

Perkins, C.

2001-01-01

Over the last few years, significant progress has been made towards siting national, purpose-built facilities for Australian radioactive waste. In 2001, after an eight year search, a preferred site and two alternatives were identified in central-north South Australia for a near-surface repository for Australian low level (low level and short-lived intermediate level) radioactive waste. Site 52a at Everts Field West on the Woomera Prohibited Area was selected as the preferred site as it performs best against the selection criteria, particularly with respect to geology, ground water, transport and security. Two alternative sites, Site 45a and Site 40a, east of the Woomera-Roxby Downs Road, were also found to be highly suitable for the siting of the national repository. A project has commenced to site a national store for intermediate (long-lived intermediate level) radioactive waste on Commonwealth land for waste produced by Commonwealth agencies. Public input has been sought on relevant selection criteria

Role of waste packages in the safety of a high level waste repository in a deep geological formation

International Nuclear Information System (INIS)

Bretheau, F.; Lewi, J.

1990-06-01

The safety of a radioactive waste disposal facility lays on the three following barriers placed between the radioactive materials and the biosphere: the waste package; the engineered barriers; the geological barrier. The function assigned to each of these barriers in the performance assessment is an option taken by the organization responsible for waste disposal management (ANDRA in France), which must show that: expected performances of each barrier (confinement ability, life-time, etc.) are at least equal to those required to fulfill the assigned function; radiation protection requirements are met in all situations considered as credible, whether they be the normal situation or random event situations. The French waste management strategy is based upon two types of disposal depending on the nature and activity of waste packages: - surface disposal intended for low and medium level wastes having half-lives of about 30 years or less and alpha activity less than 3.7 MBq/kg (0.1 Ci/t), for individual packages and less than 0.37 MBq/kg (0.01 Ci/t) in the average. Deep geological disposal intended for TRU and high level wastes. The conditions of acceptance of packages in a surface disposal site are subject to the two fundamental safety rules no. I.2 and III.2.e. The present paper is only dealing with deep geological disposal. For deep geological repositories, three stages are involved: stage preceding definitive disposal (intermediate storage, transportation, handling, setting up in the disposal cavities); stage subsequent to definitive sealing of the disposal cavities but prior to the end of operation of the repository; stage subsequent to closure of the repository. The role of the geological barrier has been determined as the essential part of long term radioactivity confinement, by a working group, set up by the French safety authorities. Essential technical criteria relating to the choice of a site so defined by this group, are the following: very low permeability

Evaluation of coupled thermo-hydro-mechanical phenomena in the near field for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Chijimatsu, Masakazu; Fujita, Tomoo; Sugita, Yutaka; Taniguchi, Wataru

2000-01-01

Geological disposal of high-level radioactive waste (HLW) in Japan is based on a multibarrier system composed of engineered and natural barriers. The engineered barriers are composed of vitrified waste confined within a canister, overpack and buffer material. Highly compacted bentonite clay is considered one of the most promising candidate buffer material mainly because of its low hydraulic conductivity and high adsorption capacity of radionuclides. In a repository of HLW, complex thermal, hydraulic and mechanical (T-H-M) phenomena will take place, involving the interactive processes between radioactive decay heat from the vitrified waste, infiltration of ground water and stress generation due to the earth pressure, the thermal loading and the swelling pressure of the buffer material. In order to evaluate the performance of the buffer material, the coupled T-H-M behaviors within the compacted bentonite have to be modelled. Before establishing a fully coupled T-H-M model, the mechanism of each single phenomenon or partially coupled phenomena should be identified. Furthermore, in order to evaluate the coupled T-H-M phenomena, the analysis model was developed physically and numerically and the adequacy and the applicability was tested though the engineered scale laboratory test and in-situ test. In this report, the investigative results for the development of coupled T-H-M model were described. This report consists of eight chapters. In Chapter 1, the necessity of coupled T-H-M model in the geological disposal project of the high-level radioactive waste was described . In Chapter 2, the laboratory test results of the rock sample and the buffer material for the coupled T-H-M analysis were shown. The rock samples were obtained from the in-situ experimental site at Kamaishi mine. As the buffer material, bentonite clay (Kunigel V1 and Kunigel OT-9607) and bentonite-sand mixture were used. In Chapter 3, in-situ tests to obtain the rock property were shown. As in-situ tests

Evaluation of coupled thermo-hydro-mechanical phenomena in the near field for geological disposal of high-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Chijimatsu, Masakazu; Fujita, Tomoo; Sugita, Yutaka; Taniguchi, Wataru [Japan Nuclear Cycle Development Inst., Tokai Works, Waste Management and Fuel Cycle Research Center, Waste Isolation Research Division, Barrier Performance Group, Tokai, Ibaraki (Japan)

2000-01-01

Geological disposal of high-level radioactive waste (HLW) in Japan is based on a multibarrier system composed of engineered and natural barriers. The engineered barriers are composed of vitrified waste confined within a canister, overpack and buffer material. Highly compacted bentonite clay is considered one of the most promising candidate buffer material mainly because of its low hydraulic conductivity and high adsorption capacity of radionuclides. In a repository of HLW, complex thermal, hydraulic and mechanical (T-H-M) phenomena will take place, involving the interactive processes between radioactive decay heat from the vitrified waste, infiltration of ground water and stress generation due to the earth pressure, the thermal loading and the swelling pressure of the buffer material. In order to evaluate the performance of the buffer material, the coupled T-H-M behaviors within the compacted bentonite have to be modelled. Before establishing a fully coupled T-H-M model, the mechanism of each single phenomenon or partially coupled phenomena should be identified. Furthermore, in order to evaluate the coupled T-H-M phenomena, the analysis model was developed physically and numerically and the adequacy and the applicability was tested though the engineered scale laboratory test and in-situ test. In this report, the investigative results for the development of coupled T-H-M model were described. This report consists of eight chapters. In Chapter 1, the necessity of coupled T-H-M model in the geological disposal project of the high-level radioactive waste was described . In Chapter 2, the laboratory test results of the rock sample and the buffer material for the coupled T-H-M analysis were shown. The rock samples were obtained from the in-situ experimental site at Kamaishi mine. As the buffer material, bentonite clay (Kunigel V1 and Kunigel OT-9607) and bentonite-sand mixture were used. In Chapter 3, in-situ tests to obtain the rock property were shown. As in-situ tests

Long-term stability of the near-field about high-level radioactive waste repository in thermo-hydro-mechanical coupling action condition

International Nuclear Information System (INIS)

Liu Yuemiao; Wang Ju; Ke Dan; Cai Meifeng

2008-01-01

It is a long-term process for the high-level radioactive waste repository, from opening, construction to end of its service. The long-term stability of the near-field is the key issue for the design of HLW repository because the opening and heat generated from the HLW. Through a nationwide investigation, Beishan area, a Gobi desert in Gansu province, is considered as a suitable candidate and GMZ bentonite deposit which located in Xinghe County, Inner Mongolia has been proposed for the supplier of buffer/backfill material for HLW geological repository in China. According to the R and D guide of high-level radioactive waste disposal in China, the 3D model of HLW repository with high-level radioactive waste, canister and buffer/backfill material is established using FLAC3D. To take into account in situ stress, geothermal gradient, groundwater, thermal relief of HLW and swelling pressure of buffer/backfill material, the evolution of temperature, stress and displacement of HLW repository under thermo-mechanical coupling, hydro-mechanical coupling and thermo-hydro-mechanical coupling conditions was analyzed respectively. The long-term stability of HLW repository in Beishan area was studied. (authors)

Development of geological disposal system for spent fuels and high-level radioactive wastes in Korea

International Nuclear Information System (INIS)

Choi, Heui Joo; Lee, Jong Youl; Choi, Jong Won

2013-01-01

Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for spent fuel) for PWR and CANDU spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR spent fuels and 16,000 MtU of CANDU spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR spent fuel since 2007. However, since no decision was made for the CANDU spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.

The IAEA's high level radioactive waste management programme

International Nuclear Information System (INIS)

Saire, D.E.

1994-01-01

This paper presents the different activities that are performed under the International Atomic Energy Agency's (IAEA) high level radioactive waste management programme. The Agency's programme is composed of five main activities (information exchange, international safety standards, R ampersand D activities, advisory services and special projects) which are described in the paper. Special emphasis is placed on the RADioactive WAste Safety Standards (RADWASS) programme which was implemented in 1991 to document international consensus that exists on the safe management of radioactive waste. The paper also raises the question about the need for regional repositories to serve certain countries that do not have the resources or infrastructure to construct a national repository

Geological disposal of radioactive wastes: national commitment, local and regional involvement

International Nuclear Information System (INIS)

2013-07-01

Long-term radioactive waste management, including geological disposal, involves the construction of a limited number of facilities and it is therefore a national challenge with a strong local/regional dimension. Public information, consultation and/or participation in environmental or technological decision-making are today's best practice and must take place at the different geographical and political scales. Large-scale technology projects are much more likely to be accepted when stakeholders have been involved in making them possible and have developed a sense of interest in or responsibility for them. In this way, national commitment, and local and regional involvement are two essential dimensions of the complex task of securing continued societal agreement for the deep geological disposal of radioactive wastes. Long-term radioactive waste management, including geological disposal, is a national challenge with a strong local/regional dimension. The national policy frameworks increasingly support participatory, flexible and accountable processes. Radioactive waste management institutions are evolving away from a technocratic stance, demonstrating constructive interest in learning and adapting to societal requirements. Empowerment of the local and regional actors has been growing steadily in the last decade. Regional and local players tend to take an active role concerning the siting and implementation of geological repositories. National commitment and local/regional involvement go hand-in-hand in supporting sustainable decisions for the geological disposal of radioactive waste

Project Guarantee 1985. Repository for high-level radioactive waste: construction and operation

International Nuclear Information System (INIS)

Anon.

1985-01-01

An engineering project study aimed at demonstrating the feasibility of constructing a deep repository for high-level waste (Type C repository) has been carried out; the study is based on a model data-set representing typical geological and rock mechanical conditions as found outside the so-called Permocarboniferous basin in the regions under investigation by Nagra in Cantons Aargau, Schaffhausen, Solothurn and Zuerich. The repository is intended for disposal of high-level waste and any intermediate-level waste from re-processing in which the concentration of long-lived alpha-emitters exceeds the permissible limits set for a Type B repository. Final disposal of high-level waste is in subterranean, horizontally mined tunnels and of intermediate-level waste in underground vertical silos. The repository is intended to accomodate a total of around 6'000 HWL-cylinders (gross volume of around 1'200 m3) and around 10'000 m3 of intermediate-level waste. The total excavated volume is around 1'100'000 m3 and a construction time for the whole repository (up to the beginning of emplacement) of around 15 years is expected. For the estimated 50-year emplacement operations, a working team of around 60 people will be needed and a team of around 160 for the simultaneous tunnelling operations and auxiliary work. The project described in the present report permits the conclusion that construction of a repository for high-level radioactive waste and, if necessary, spent fuel-rods is feasible with present-day technology

A perspective on demonstrating compliance with standards for disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Smith, E.D.; O'Kelley, G.D.; Sjoreen, A.L.

1985-01-01

A perspective which the authors have developed on the problem of demonstrating that geologic repositories for the disposal of high-level radioactive wastes will comply with system performance standards is discussed. Their viewpoint arises from a concern that the U.S. Environmental Protection Agency's proposed environmental standard for high-level waste disposal appears to require demonstrations of compliance which are incompatible with scientific knowledge; i.e., the standard does not take into account the likely importance of unquantifiable and unresolvable uncertainty in repository performance-assessment models. A general approach to demonstrations of compliance is proposed which is thought to be compatible with the kinds of technical information that will be available for judging long-term repository performance. The authors' approach emphasizes the importance of investigating alternative conceptual models and lines of reasoning in evaluating repository performance and the importance of subjective scientific judgment in the decision-making process. (Auth.)

High-level radioactive waste in Canada. Background paper

International Nuclear Information System (INIS)

Fawcett, R.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab

High-level radioactive waste in Canada. Background paper

Energy Technology Data Exchange (ETDEWEB)

Fawcett, R [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab.

Geological study of radioactive waste repositories

International Nuclear Information System (INIS)

Oyama, Takahiro; Kitano, Koichi

1987-01-01

The investigation of the stability and the barrier efficiency of the deep underground radioactive waste repositories become a subject of great concern. The purpose of this paper is to gather informations on the geology, engineering geology and hydrogeology in deep galleries in Japan. Conclusion can be summarised as follows: (1) The geological structure of deep underground is complicated. (2) Stress in deep underground is greatly affected by crustal movement. (3) Rock-burst phenomena occur in the deep underground excavations. (4) In spite of deep underground, water occasionally gush out from the fractured zone of rock mass. These conclusion will be useful for feasibility study of underground waste disposal and repositories in Japan. (author)

Geological characterisation of potential disposal areas for radioactive waste from Risoe, Denmark

International Nuclear Information System (INIS)

Gravesen, P.; Binderup, M.; Nilsson, B.; Schack Pedersen, S.A.

2011-01-01

Low- and intermediate-level radioactive waste from the Danish nuclear research facility, Risoe, includes construction materials from the reactors, different types of contaminated material from the research projects and radioactive waste from hospitals, industry and research institutes. This material must be stored in a permanent disposal site in Denmark for at least 300 years. The latter study was conducted by the Geological Survey of Denmark and Greenland (GEUS) and the aim was to locate a sediment or rock body with low permeability down to 100-300 m below the ground surface. GEUS was given the task to locate approximately 20 potential disposal areas. The survey resulted in the selection of 22 areas throughout Denmark. Six of these areas are preferred on geological and hydrogeological criteria. (LN)

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Selection of thermodynamic data of selenium

International Nuclear Information System (INIS)

Doi, Reisuke; Kitamura, Akira; Yui, Mikazu

2010-02-01

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU radioactive wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of selenium was carried out. Selection of thermodynamic data of selenium was based on a thermodynamic database of selenium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). The remarks of a thermodynamic database by OECD/NEA found by the authors were noted in this report and then thermodynamic data was reviewed after surveying latest literatures. Some thermodynamic values of iron selenides were not selected by the OECD/NEA due to low reliability. But they were important for the performance assessment of geological disposal of radioactive wastes, so we selected them as a tentative value with specifying reliability and needs of the value to be determined. (author)

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

International Nuclear Information System (INIS)

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

2001-01-01

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

The Influence of Engineering-Geological Conditions on the Construction of the Radioactive Waste Dump

Directory of Open Access Journals (Sweden)

Jozef Kuzma

2007-01-01

Full Text Available A secure stability and reliable serviceability of the radioactive dump is a difficult engineering problem. Due to the difficult geological formations determined mainly by a high compressibility, the low shear strength of soils, and the high ground water level, or a high upward hydrostatic pressure these demands will increase. An influence of the required reliability and the lifespan on the structure of these specific objects is considerable. In this contribution, we are trying to contribute to the problem of solving these difficulties and complicated problems.

Office of Geologic Repositories quality assurance plan for high-level radioactive waste repositories

International Nuclear Information System (INIS)

1986-08-01

This document sets forth geologic repository program-wide quality assurance program requirements and defines management's quality assurance responsibilities for the Office of Geologic Repositories and its projects. (LM)

Study on high-level waste geological disposal metadata model

International Nuclear Information System (INIS)

Ding Xiaobin; Wang Changhong; Zhu Hehua; Li Xiaojun

2008-01-01

This paper expatiated the concept of metadata and its researches within china and abroad, then explain why start the study on the metadata model of high-level nuclear waste deep geological disposal project. As reference to GML, the author first set up DML under the framework of digital underground space engineering. Based on DML, a standardized metadata employed in high-level nuclear waste deep geological disposal project is presented. Then, a Metadata Model with the utilization of internet is put forward. With the standardized data and CSW services, this model may solve the problem in the data sharing and exchanging of different data form A metadata editor is build up in order to search and maintain metadata based on this model. (authors)

The suitability of Finnish bedrock to the final disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Vuorela, P.; Hakkarainen, V.

1982-12-01

A regional investigation of the suitability of Finnish bedrock to the final disposal of high-level radioactive waste is described. International geological criteria are applied to Finnish bedrock conditions. The main bedrock units are classified into different areas as concerning to recommendations for further site selection investigations. The Pre-Cambrian crystalline rocks are generally of tight and strong composition and a major problem from the standpoint of waste disposal is fracturing. On the other hand, fractures are quite unevenly distributed in Finland and the bedrock seems to consist of stabile blocks surrounded by fracture zones. Crustal movements between the different bedrock blocks are in Finland at most only tenths of millimeters a year, and the movements are concentrated in the fracture zones. The fracture pattern also controls the hydrogeological system of the bedrock as the main groundwater flow occurs along the fractures. The fracturing thus has an influence on the stability as well as the hydrogeological conditions of the bedrock. The regional recommendations for further site selection studies are based on geological criteria, such as fracturing, seismisity and economic resources. Other criteria, such as topography and erosion, are less significant in comparison. A number of different criteria are likely to prove significant later in more detailed local site investigation studies. The most favorable regions for more detailed investigations contain the granitic rocks of Central Finland and some of them are also to be found in northern and eastern parts of the country. Almost none of the main bedrock units can be classified as completely unsuitable for site selection investigations. Massifs large enough for the final disposal of high-level radioactive waste can be found through detailed surveys in most parts of Finland because of the heterogeneity of the bedrock

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.)

Geologic disposal of radioactive waste, 1983

International Nuclear Information System (INIS)

Pigford, T.H.

1983-10-01

Geologic repositories for radioactive waste are evolving from conceptualization to the development of specific designs. Estimates of long-term hazards must be based upon quantitative predictions of environmental releases over time periods of hundreds of thousands of years and longer. This paper summarizes new techniques for predicting the long-term performance of repositories, it presents estimates of future environmental releases and radiation doses that may result for conceptual repositories in various geologic media, and it compares these predictions with an individual dose criterion of 10 -4 Sv/y. 50 references, 11 figures, 6 tables

Partitioning of high level liquid waste: experiences in plant level adoption

International Nuclear Information System (INIS)

Manohar, Smitha; Kaushik, C.P.

2016-01-01

High Level Radioactive Wastes are presently vitrified in borosilicate matrices in all our back end facilities in our country. This is in accordance with internationally endorsed methodology for the safe management of high level radioactive wastes. Recent advancements in the field of partitioning technology in our group, has presented us with an opportunity to have a fresh perspective on management of high level liquid radioactive wastes streams, that emanate from reprocessing operations. This paper will highlight our experiences with respect to both partitioning studies and vitrification practices, with a focus on waste volume reduction for final disposal. Incorporation of this technique has led to the implementation of the concept of recovering wealth from waste, a marked decrease on the load of disposal in deep geological repositories and serve as a step towards the vision of transmutation of long lived radionuclides

The United States program for the safety assessment of geologic disposal of commercial radioactive wastes

International Nuclear Information System (INIS)

Claiborne, H.C.

1977-01-01

The safe disposal of commercial radioactive wastes in deep geologic formations is the goal of the National Waste Terminal Storage (NWTS) Program. Safety assessment begins with selection of a disposal site; that is, all geologic and hydrologic factors must indicate long-term stability of the formation and prospective isolation of wastes from circulating ground waters for hundreds of thousands of years. The long-term stability of each site under thermal loading must then be demonstrated by sophisticated rock mechanic analyses. Therefore, it can be expected that the sites that are chosen will effectively isolate the waste for a very long period of time. However, to help provide answers on the mechanisms and consequences of an unlikely breach in the integrity of the repository, a Waste Isolation Safety Assessment Program (WISAP) is studied. The overall objective of this program is an assessment of the safety associated with the long-term disposal of high-level radioactive waste in a geologic formation. This objective will be achieved by developing methods and generating data necessary to characterize the safety of generic geological waste disposal concepts, which are to be applied in the assessment of specific sites. It is expected that no one particular model will suffice. Both deterministic and probabilistic approaches will be used, and the entire spectrum of phenomena that could influence geologic isolation will be considered

DEVELOPMENT OF GEOLOGICAL DISPOSAL SYSTEMS FOR SPENT FUELS AND HIGH-LEVEL RADIOACTIVE WASTES IN KOREA

Directory of Open Access Journals (Sweden)

HEUI-JOO CHOI

2013-02-01

Full Text Available Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for spent fuel for PWR and CANDU spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR spent fuels and 16,000 MtU of CANDU spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR spent fuel since 2007. However, since no decision was made for the CANDU spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.

The basic concept for the geological surveys

International Nuclear Information System (INIS)

Deguchi, Akira; Takahashi, Yoshiaki

1998-01-01

Before the construction of high level radioactive waste repository, the implementing entity will go through three siting stages for the repository. In each of those three stages, the implementing entity will carry out geological surveys. In this report, the concept for the geological surveys is described, on the basic of 'The policies for the high level radioactive waste disposal (a tentative draft)' issued by the Atomic Energy Commission in July, 1997. (author)

Some historical background to the IAEA Definition and Recommendations concerning high-level radioactive wastes or other high-level radioactive matter unsuitable for dumping at sea

International Nuclear Information System (INIS)

Nishiwaki, Y.

1981-01-01

The need for internationally acceptable standards and regulations for preventing pollution of the sea by radioactive materials was recognized by the United Nations Conference on the Law of the Sea, which adopted the Convention on the High Seas in April 1958. Article 25 of the Convention provides that ''every State shall take measures to prevent pollution of the seas from the dumping of radioactive wastes, taking into account any standards and regulations which may be formulated by the competent international organizations.'' The Conference also adopted a resolution recommending that the IAEA pursue studies and take action to assist States in controlling the discharge of radioactive materials into the sea. When the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter was adopted at the Intergovernmental Conference in London, 1972, the IAEA was given specific responsibilities to define criteria and standards for dealing with the questions of sea disposal of radioactive wastes. The IAEA Definition and Recommendations concerning ''high-level radioactive wastes or other high-level radioactive matter unsuitable for dumping at sea'' identify material, the radioactive content of which is at such a level that the Parties to the Convention would wish to prevent any participating State from issuing a special permit even after a detailed appraisal of the safety of the proposed operation, and even for the sector of the marine environment furthest removed from man, i.e. the deep sea with depth greater than 4000 m. Some historical background to these problems is discussed and some of the Japanese findings of the deep sea survey in the Pacific are introduced for comparison with the North Atlantic data which formed a basis of the IAEA Definition and Recommendations for the London Dumping Convention

Grimsel test site. Research on safe geological disposal of radioactive waste

International Nuclear Information System (INIS)

2010-07-01

The Grimsel Test Site is located at an altitude of 1730 meters in the granitic formations of the Aare Massif. Some 300 million years ago, magmas solidified to form granitic rocks in the Grimsel area. New molten masses flowed into fissures of the cooling rock and formed dyke rocks. During the alpine orogeny around 40 million years ago, the rocks of the Aare Massif were passed over by the northwards-moving alpine layers and subsided by around 12 kilometres. The rocks were then overprinted under high temperature and pressure conditions and shear zones and fracture systems were formed. Uplift (0.5 to 0.8 mm/a) and erosion processes, which are still continuing today, brought the rocks of the Aare Massif to the surface once more. The mineral fractures for which the Grimsel area is famous, formed around 14 million years ago. Deep in the rock, the range of geological conditions found in the laboratory present ideal boundary conditions for investigating the functioning of both the geological and engineered barriers of deep repositories. Projects that look at the disposal concepts on a large scale are also an important aspect of the work at the Test Site. A radiation controlled zone allows radionuclides to be used under monitored conditions, giving a direct insight into the transport of radioactive substances in the rock. Around 25 partner organisations from various countries are involved in the projects at the Test Site. The European Union and the Swiss State Secretariat for Education and Research provide financial support to several experiments. In Switzerland, deep geological disposal is required by law for all types of radioactive waste. Field investigations for determining the suitability of potential disposal sites are an important component of a waste management programme. The field work is complemented by laboratory studies, investigations of relevant natural processes and research projects in underground rock laboratories; these provide a better understanding of the

Grimsel test site. Research on safe geological disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-15

The Grimsel Test Site is located at an altitude of 1730 meters in the granitic formations of the Aare Massif. Some 300 million years ago, magmas solidified to form granitic rocks in the Grimsel area. New molten masses flowed into fissures of the cooling rock and formed dyke rocks. During the alpine orogeny around 40 million years ago, the rocks of the Aare Massif were passed over by the northwards-moving alpine layers and subsided by around 12 kilometres. The rocks were then overprinted under high temperature and pressure conditions and shear zones and fracture systems were formed. Uplift (0.5 to 0.8 mm/a) and erosion processes, which are still continuing today, brought the rocks of the Aare Massif to the surface once more. The mineral fractures for which the Grimsel area is famous, formed around 14 million years ago. Deep in the rock, the range of geological conditions found in the laboratory present ideal boundary conditions for investigating the functioning of both the geological and engineered barriers of deep repositories. Projects that look at the disposal concepts on a large scale are also an important aspect of the work at the Test Site. A radiation controlled zone allows radionuclides to be used under monitored conditions, giving a direct insight into the transport of radioactive substances in the rock. Around 25 partner organisations from various countries are involved in the projects at the Test Site. The European Union and the Swiss State Secretariat for Education and Research provide financial support to several experiments. In Switzerland, deep geological disposal is required by law for all types of radioactive waste. Field investigations for determining the suitability of potential disposal sites are an important component of a waste management programme. The field work is complemented by laboratory studies, investigations of relevant natural processes and research projects in underground rock laboratories; these provide a better understanding of the

Environmental remediation of high-level nuclear waste in geological repository. Modified computer code creates ultimate benchmark in natural systems

International Nuclear Information System (INIS)

Peter, Geoffrey J.

2011-01-01

Isolation of high-level nuclear waste in permanent geological repositories has been a major concern for over 30 years due to the migration of dissolved radio nuclides reaching the water table (10,000-year compliance period) as water moves through the repository and the surrounding area. Repositories based on mathematical models allow for long-term geological phenomena and involve many approximations; however, experimental verification of long-term processes is impossible. Countries must determine if geological disposal is adequate for permanent storage. Many countries have extensively studied different aspects of safely confining the highly radioactive waste in an underground repository based on the unique geological composition at their selected repository location. This paper discusses two computer codes developed by various countries to study the coupled thermal, mechanical, and chemical process in these environments, and the migration of radionuclide. Further, this paper presents the results of a case study of the Magma-hydrothermal (MH) computer code, modified by the author, applied to nuclear waste repository analysis. The MH code verified by simulating natural systems thus, creating the ultimate benchmark. This approach based on processes similar to those expected near waste repositories currently occurring in natural systems. (author)

Radon and Radioactivity in Spanish Spas of Different Geological Formations

International Nuclear Information System (INIS)

Rodenas, C.; Gomez, J.; Soto, J.; Quindos, L.S.; Maraver, F.

2009-01-01

Gross-α and gross-β activity, 222 Rn and 226 Ra of 82 thermal water samples in Spain were performed in order to determine their radioactivity. Gross- α and gross- β activity ranged from LLD to 17 Bq.l - 1 and from LLD to 60 Bq.l - 1, respectively. 226 Ra concentrations ranged from - 1. 222 Rn concentrations ranged from - 1. The observed values were correlated with the geological formations and structure of the area. Significant differences have been found depending on the geological characteristics of the area of the reference. The highest levels are usually found in granites but concentrations vary considerably between spring waters within each lithology

Study on the high level radioactive wastes geological isolation seen from the social acceptance of science and technology. (1) The explanation based on the principle of risk and benefit for another field specialist

International Nuclear Information System (INIS)

Wada, Ryutaro; Tanaka, Satoru; Nagasaki, Shinya

2009-01-01

Generally speaking, a vast, advanced and unfamiliar science and technology is unacceptable by public for the fear of its unknown nature. The siting problem for the disposal of high level radioactive wastes is one of the typical examples. This study examined the desirable research scheme for geological disposal of the high level radioactive wastes seen from social acceptance of science and technology in the deductive approach by the technical essence described in the first report. As the safety is the most prioritized concern in the research of radioactive waste disposal, the correlation between safety and cost has not been argued. Therefore, the argument has only turned in seeking for limitless safety without paying attention to an economic principle. In this report, as the examination evolving from a social acceptability, the author tries to explain the safety together with cost information in accordance with the principle of the risk benefit. As a result, it turned out that the relation between the existing Japanese default proposal (H12 report) and overseas examples can be figured out to explain their relative position by the safety and cost correlation diagram made in accordance with the risk benefit principle. The nuclear field specialist can discuss a relative location of the Japanese disposal concept by this correlation diagram with another field specialist. (author)

International Approaches for Nuclear Waste Disposal in Geological Formations: Geological Challenges in Radioactive Waste Isolation—Fifth Worldwide Review

Energy Technology Data Exchange (ETDEWEB)

Faybishenko, Boris [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Birkholzer, Jens [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sassani, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Swift, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-04-26

The overall objective of the Fifth Worldwide Review (WWR-5) is to document the current state-of-the-art of major developments in a number of nations throughout the World pursuing geological disposal programs, and to summarize challenging problems and experience that have been obtained in siting, preparing and reviewing cases for the operational and long-term safety of proposed and operating nuclear waste repositories. The scope of the Review is to address current specific technical issues and challenges in safety case development along with the interplay of technical feasibility, siting, engineering design issues, and operational and post-closure safety. In particular, the chapters included in the report present the following types of information: the current status of the deep geological repository programs for high level nuclear waste and low- and intermediate level nuclear waste in each country, concepts of siting and radioactive waste and spent nuclear fuel management in different countries (with the emphasis of nuclear waste disposal under different climatic conditions and different geological formations), progress in repository site selection and site characterization, technology development, buffer/backfill materials studies and testing, support activities, programs, and projects, international cooperation, and future plans, as well as regulatory issues and transboundary problems.

Spanish high level radioactive waste management system issues

International Nuclear Information System (INIS)

Espejo, J.M.; Beceiro, A.R.

1992-01-01

The Empresa Nacional de Residuos Radiactivos, S.A. (ENRESA) has been limited liability company to be responsible for the management of all kind of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high - level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international cooperation are also included

A proposed classification system for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1989-01-01

On the basis of the definition of high-level wastes (HLW) in the Nuclear Waste Policy Act of 1982 and previous descriptions of reprocessing wastes, a definition is proposed based on the concept that HLW is any waste which is highly radioactive and requires permanent isolation. This conceptual definition of HLW leads to a two-dimensional waste classification system in which one axis, related to 'highly radioactive', is associated with shorter-term risks from waste management and disposal due to high levels of decay heat and external radiation, and the other axis, related to 'requires permanent isolation', is associated with longer-term risks from waste disposal. Wastes that are highly radioactive are defined quantitatively as wastes with a decay heat (power density) greater than 50 W/m 3 or an external dose-equivalent rate greater than 100 rem/h (1 Sv/h) at a distance of 1 m from the waste, whichever is more restrictive. Wastes that require permanent isolation are defined quantitatively as wastes with concentrations of radionuclides greater than the Class-C limits that are generally acceptable for near-surface land disposal, as obtained from the Nuclear Regulatory Commission's 10 CFR Part 61 and its associated methodology. This proposal leads to similar definitions of two other waste classes: transuranic (TRU) waste and equivalent is any waste that requires permanent isolation but is not highly radioactive; and low-level waste (LLW) is any waste that does not require permanent isolation, without regard to whether or not it is highly radioactive. 31 refs.; 3 figs.; 4 tabs

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

International Nuclear Information System (INIS)

Arup, O.

1985-01-01

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

Evaluation of radionuclide concentrations in high-level radioactive wastes

International Nuclear Information System (INIS)

Fehringer, D.J.

1985-10-01

This report describes a possible approach for development of a numerical definition of the term ''high-level radioactive waste.'' Five wastes are identified which are recognized as being high-level wastes under current, non-numerical definitions. The constituents of these wastes are examined and the most hazardous component radionuclides are identified. This report suggests that other wastes with similar concentrations of these radionuclides could also be defined as high-level wastes. 15 refs., 9 figs., 4 tabs

Deep geologic repository for low and intermediate radioactive level waste in Canada

International Nuclear Information System (INIS)

Liu Jianqin; Li Honghui; Sun Qinghong; Yang Zhongtian

2012-01-01

Ontario Power Generation (OPG) is undergoing a project for the long-term management of low and intermediate level waste (LILW)-a deep geologic repository (DGR) project for low and intermediate level waste. The waste source term disposed, geologic setting, repository layout and operation, and safety assessment are discussed. It is expected to provide reference for disposal of low and intermediate level waste that contain the higher concentration of long-lived radionuclides in China. (authors)

Low-level radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

Ishihara, T [Radioactive Waste Management Center, Tokyo (Japan)

1980-08-01

In the development and utilization of nuclear energy, variety of radioactive wastes arise. A largest part is low level radioactive wastes. In Japan, they are concentrated and solidified, and stored in drums. However, no low level wastes have yet been finally disposed of; there are now about 260,000 drums of such wastes stored on the sites. In Japan, the land is narrow, and its structure is geologically unstable, so that the sea disposal is sought. On the other hand, the development of technology for the ground disposal has lagged behind the sea disposal until recently because of the law concerned. The following matters are described: for the sea disposal, preparatory technology studies, environment safety assessment, administrative measures, and international control; for the ground disposal, experiments, surveys, disposal site selection, and the concept of island repositories.

Prediction of long term stability for geological disposal of radioactive waste

International Nuclear Information System (INIS)

Sasaki, Takeshi; Morikawa, Seiji; Koide, Hitoshi; Kono, Itoshi

1998-01-01

On geological disposal of radioactive wastes, study on prediction of diastrophism has been paid many attentions, and then long term future prediction ranging from some thousands to some tends thousands years may be necessary for some target nuclides. As there are various methods in the future prediction, it is essential to use a computational dynamic procedure to conduct a quantitative prediction. However, it causes an obstacle to advancement of the prediction method that informations on deep underground have a lot of uncertain elements because of their few and indirect data. In this paper, a long term prediction procedure of diastrophism relating to geological disposal of radioactive wastes with low level but isolation terms required to some thousands years was investigated and each one example was shown on flow of the investigation and its modeling method by using the finite element method. It seems to be a key to upgrade accuracy of future diastrophism prediction how an earth fault can be analyzed. And, as the diastrophism is a long term and complex phenomenon and its prediction has many uncertain elements, it is important to judge comprehensively results of its numerical analysis geologically and on rock engineering. (G.K.)

Risk comparison of different treatment and disposal strategies of high level liquid radioactive waste

International Nuclear Information System (INIS)

Fang Dong

1997-01-01

The risk of different treatment and disposal strategies of high level liquid radioactive waste from spent fuel reprocessing is estimated and compared. The conclusions obtained are that risk difference from these strategies is very small and high level liquid waste can be reduced to middle and low level waste, if the decontamination factor for 99 Tc is large enough, which is the largest risk contributor in the high level radioactive waste from spent fuel reprocessing. It is also shown that the risk of high level radioactive waste could be reduced by the technical strategy of combining partitioning and transmutation

High Level Radioactive Waste Management: Proceedings of the second annual international conference

International Nuclear Information System (INIS)

1991-01-01

The final disposal of high level radioactive waste (HLW) has been one of the most arduous problems facing the nuclear industry. This issue has many facets, which are addressed in these proceedings. The papers herein contain the most current information regarding the conditioning and disposal of HLW. Most of the needs are technical in nature, such as the best form of the waste, the integrity of storage containers, design and construction of a repository, and characterization of the geology of a repository to provide assurance that radioactive and other hazardous materials will not reach the surrounding environment. Many of the papers discuss non-US programs. Continued international cooperation and technology exchange is essential. There are other concerns that must be addressed before the final emplacement of HLW. Some of the other issues addressed in these proceedings are conformance to regulations, transportation, socioeconomics, and public education. Any impediments in these areas must be resolved along with the scientific issues before final waste disposal. This conference provides a forum for information exchange. The papers in these proceedings will provide the basis for future planning and decisions. Continued cooperation of the technical community will ultimately result in the safe disposal of HLW. Individual abstracts are indexed separately for the data base

Quantitative performance allocation of multi-barrier system for high-level radioactive waste disposal

International Nuclear Information System (INIS)

Ahn, Joon-Hong; Ikeda, Takao; Ohe, Toshiaki

1995-01-01

Performance assessment of each barrier consisting of geologic disposal system for high-level radioactive wastes is carried out quantitatively, and key radionuclides and parameters are pointed out. Chemical compositions and solubilities of radionuclides under repository conditions are determined by PHREEQE code staring from compositions of granitic groundwater observed in Japan. Glass dissolution analysis based on mass transfer theory and precipitation analysis have been done in order to determine the inner boundary condition for radionuclide diffusion through a bentonite-filled buffer region, where multi-member decay chain and isotopic sharing of solubility at the inner boundary are considered. Natural barrier is treated as homogeneous porous rock, or porous rock with infinite planar fractures. Performance of each barrier is evaluated in terms of non-dimensionalized hazard defined as the ratio of annual radioactivity release from each barrier to the annual limit on intake. At the outer edge of the engineered barriers, 239 Pu is the key unclide to the performance, whereas at the exit of the natural barrier, weakly-sorbing fission product nuclides such as 135 Cs, 129 I and 99 Tc dominate the hazard. (author) 50 refs

NWTS program criteria for mined geologic disposal of nuclear waste: functional requirements and performance criteria for waste packages for solidified high-level waste and spent fuel

International Nuclear Information System (INIS)

1982-07-01

The Department of Energy (DOE) has primary federal responsibility for the development and implementation of safe and environmentally acceptable nuclear waste disposal methods. Currently, the principal emphasis in the program is on emplacement of nuclear wastes in mined geologic repositories well beneath the earth's surface. A brief description of the mined geologic disposal system is provided. The National Waste Terminal Storage (NWTS) program was established under DOE's predecessor, the Energy Research and Development Administration, to provide facilities for the mined geologic disposal of radioactive wastes. The NWTS program includes both the development and the implementation of the technology necessary for designing, constructing, licensing, and operating repositories. The program does not include the management of processing radioactive wastes or of transporting the wastes to repositories. The NWTS-33 series, of which this document is a part, provides guidance for the NWTS program in the development and implementation of licensed mined geologic disposal systems for solidified high-level and transuranic (TRU) wastes. This document presents the functional requirements and performance criteria for waste packages for solidified high-level waste and spent fuel. A separate document to be developed, NWTS-33(4b), will present the requirements and criteria for waste packages for TRU wastes. The hierarchy and application of these requirements and criteria are discussed in Section 2.2

Siting the high level radioactive waste repository in the United States

International Nuclear Information System (INIS)

Tourtellotte, J.

1992-01-01

For more than twenty-five years after the National Academy of Science issued its 1957 report recommending a Mined Geologic Disposal System (''MGDS'') for high level radioactive waste, no substantial progress was made in selecting and siting a repository. The United States Congress attempted to give substantive and procedural direction to the program in the Nuclear Waste Policy Act of 1982. Seeing that very little had been accomplished some five years later, Congress gave further direction and tentatively selected a single site, Yucca Mountain in Nevada, in the Nuclear Waste Policy Act Amendments of 1987. Selection of the Yucca Mountain site created a political conflict between federal and state authorities. Until recently, that conflict stalled the site characterization and evaluation program. Standards development under a polycentric regulatory regime has also been slow and has created a number of technical, legal and policy controversies. The Environmental Protection Agency (EPA), charged with setting radiation protection rules, may be developing regulatory standards which are technically unachievable and, therefore, legally unprovable in a licensing proceeding. The Nuclear Regulatory Commission (NRC), having the responsibility for licensing and setting performance objectives, may be taking an overly conservative approach. This approach could seriously impact the cost and may preclude the ability to reach an affirmative finding on license issuance. The Department of Energy (DOE) has responsibility for siting, construction and operation of the repository. In so doing, DOE must apply both EPA and NRC standards. To the extent that EPA and NRC standards are untimely, poorly defined, unrealistic, inconsistent, and technically or legally unsound, DOE may be forestalled from fulfilling its responsibilities. The US must rethink its approach to siting the high level radioactive waste repository and take realistic, timely action to preserve the nuclear option. (Author)

The implementing geological disposal of radioactive waste technology platform main achievement in 2015

International Nuclear Information System (INIS)

Delay, J.; Garcia, M.; Kowe, R.

2015-01-01

After decades of bilateral and multilateral cooperation, several European waste management organizations decided, under the auspices of the European Commission (EC), to join their forces to tackle the remaining research, development and demonstration (RD&D) challenges associated with the implementation of their respective geological disposal programs. The main objectives of the Implementing geological disposal of radioactive waste technology platform (IGD-TP) are to initiate and carry out collaborative actions in Europe to tackle the remaining research, development and demonstration (RD&D) challenges with a view to advancing the implementation of geological disposal programmes for high-level and long-lived waste in Europe. This paper presents the organisation of the work and the main Joint activities and projects to date, initiated by the IGD-TP members and supported for some of them by the European Commission under the FP7 framework programme and in the near future under the Horizon 2020 programme. (authors)

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)

Radioactive Waste Management Research Program Plan for high-level waste: 1987

International Nuclear Information System (INIS)

1987-05-01

This plan will identify and resolve technical and scientific issues involved in the NRC's licensing and regulation of disposal systems intended to isolate high level hazardous radioactive wastes (HLW) from the human environment. The plan describes the program goals, discusses the research approach to be used, lays out peer review procedures, discusses the history and development of the high level radioactive waste problem and the research effort to date and describes study objectives and research programs in the areas of materials and engineering, hydrology and geochemistry, and compliance assessment and modeling. The plan also details the cooperative interactions with international waste management research programs. Proposed Earth Science Seismotectonic Research Program plan for radioactive waste facilities is appended

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

International Nuclear Information System (INIS)

Wen, Zhijian

2005-01-01

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

Numerical Model of Fluid Flow through Heterogeneous Rock for High Level Radioactive Waste Disposal

International Nuclear Information System (INIS)

Shirai, M.; Chiba, R.; Takahashi, T.; Hashida, T.; Fomin, S.; Chugunov, V.; Niibori, Y.

2007-01-01

An international consensus has emerged that deep geological disposal on land is one of the most appropriate means for high level radioactive wastes (HLW). The fluid transport is slow and radioactive elements are dangerous, so it's impossible to experiment over thousands of years. Instead, numerical model in such natural barrier as fractured underground needs to be considered. Field observations reveal that the equation with fractional derivative is more appropriate for describing physical phenomena than the equation which is based on the Fick's law. Thus, non-Fickian diffusion into inhomogeneous underground appears to be important in the assessment of HLW disposal. A solute transport equation with fractional derivative has been suggested and discussed in literature. However, no attempts were made to apply this equation for modeling of HLW disposal with account for the radioactive decay. In this study, we suggest the use of a novel fractional advection-diffusion equation which accounts for the effect of radioactive disintegration and for interactions between major, macro pores and fractal micro pores. This model is fundamentally different from previous proposed model of HLW, particularly in utilizing fractional derivative. Breakthrough curves numerically obtained by the present model are presented for a variety of rock types with respect to some important nuclides. Results of the calculation showed that for longer distance our model tends to be more conservative than the conventional Fickian model, therefore our model can be said to be safer

Feasibility of disposal of high-level radioactive waste into the seabed. Volume 1: Overview of research and conclusions

International Nuclear Information System (INIS)

1988-01-01

One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This volume provides an overview of the research and a summary of the results

Spanish high level radioactive waste management system issues

International Nuclear Information System (INIS)

Ulibarri, A.; Veganzones, A.

1993-01-01

The Empresa Nacional de Residuous Radiactivos, S.A. (ENRESA) was set up in 1984 as a state-owned limited liability company to be responsible for the management of all kinds of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high-level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international co-operational are also included

United States high-level radioactive waste management program: Current status and plans

International Nuclear Information System (INIS)

Williams, J.

1992-01-01

The inventory of spent fuel in storage at reactor sites in the United States is approximately 20,000 metric tons heavy metal (MTHM). It is increasing at a rate of 1700 to 2100 MTHM per year. According to current projections, by the time the last license for the current generation of nuclear reactors expires, there will be an estimated total of 84,000 MTHm. No commercial reprocessing capacity exists or is planned in the US. Therefore, the continued storage of spent fuel is required. The majority of spent fuel remains in the spent fuel pools of the utilities that generated it. Three utilities are presently supplementing pool capacity with on-site dry storage technologies, and four others are planning dry storage. Commercial utilities are responsible for managing their spent fuel until the Federal waste management system, now under development, accepts spent fuel for storage and disposal. Federal legislation charges the Office of Civilian Radioactive Waste Management (OCRWM) within the US Department of Energy (DOE) with responsibility for developing a system to permanently dispose of spent fuel and high level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. We are developing a waste management system consisting for three components: a mined geologic repository, with a projected start date of 2010; a monitored retrievable storage facility (MRS), scheduled to begin waste acceptance in 1998; and a transportation system to support MRS and repository operations. This paper discusses the background and framework for the program, as well as the current status and plans for management of spent nuclear fuel at commercial utilities; the OCRWM's development of a permanent geologic repository, an MRS, and a transportation system; the OCRWM's safety approach; the OCRWM's program management initiatives; and the OCRWM's external relations activities

[US Geological Survey research in radioactive waste disposal, fiscal year 1980:] Search for potential [disposal] sites

International Nuclear Information System (INIS)

Dixon, G.L.; Glanzman, V.M.

1982-01-01

The objective is to locate and characterize rock masses at the NTS and in southern Nevada suitable as host media for high-level radioactive wastes; to describe the areal and depth distribution and structural integrity of these rock masses; and to assess the potential for contaminant release by hydrologic transport, or as a result of tectonic, and (or) volcanic activity. From previous geologic work at NTS, the general geology is well known. Areas likely to have suitable host rocks and hydrologic conditions at depths appropriate for a repository are evaluated by detailed surface mapping, surface geophysical methods, exploratory drilling, and geophysical techniques. 10 refs., 1 figs

Encapsulating of high-level radioactive waste with use of pyrocarbon and silicon carbide coatings

International Nuclear Information System (INIS)

Chernikov, A.

2007-01-01

It is known that high-level radioactive waste (HLW) constitute a real danger to biosphere, especially that their part, which contains transuranium and long-lived radionuclides resulting during reprocessing of nuclear fuel industrial and power reactors. Such waste contains approximately 99 % of long-lived fission products and transplutonium elements. At present, the concept of multi barrier protection of biosphere from radioactive waste is generally acknowledged. The main barriers are the physicochemical form of waste and enclosing strata of geological formation at places of waste-disposal. Applied methods of solidification of HLW with preparation of phosphatic and borosilicate glasses do not guarantee in full measure safety of places of waste-disposal of solidified waste in geological formations during thousand years. One promising way to improve HLW handling safety is placing of radionuclides in mineral-like matrixes similar to natural materials. The other possible way to increase safety of HLW disposal places is suggested for research by experts of Russian research institutes, for example, in the proposal for the Project of ISTC and considered in the present report, is to introduce an additional barrier on a radionuclides migration path by coating of HLW particles. Unique protective properties of pyrocarbon and silicon carbide such as low coefficients of diffusion of gaseous and solid fission products and high chemical and radiation stability [1] attract attention to these materials for coating of solidified HLW. The objective of the Project is the development of method of HLW encapsulating with use of pyrocarbon and silicon carbide coatings. To gain this end main direction of researches, including analysis of various encapsulation processes of fractionated HLW, and expected results are presented. Realization of the Project will allow to prove experimentally the efficiency of the proposed approach in the solution of the problem of HLW conditioning and ecological

The disposal of high level radioactive waste in argillaceous host rocks identification of parameters, constraints and geological assessment priorities

International Nuclear Information System (INIS)

Horseman, S.T.

1994-01-01

The purpose of this report, commissioned by ENRESA, is to examine the characteristics, properties and responses of argillaceous media (clays and more indurated mudrocks) in some detail in order to identify the main parameters that will influence the radiological safety of a deep underground facility for the disposal of high-level radioactive wastes (HLW) and to highlight possible constraints and other important issues relating to the construction, operation and performance of such a facility

Status of geohydrologic screening of the Basin and Range Province for isolation of high-level radioactive waste

International Nuclear Information System (INIS)

Bedinger, M.S.; Sargent, K.A.; Langer, W.H.

1984-01-01

Screening of the Basin and Range Province by the US Geological Survey for favorable environments for isolation of high-level radioactive waste began in 1981. The study is concerned with geologic and hydrologic factors, emphasizing the identification of environments that can provide multiple natural barriers to radionuclide migration. The term multiple barriers includes man-made barriers and natural barriers in the form of specified hydrodynamic, geochemical, and geologic characteristics that would impede radionuclide transport. The natural barriers of most significance include: (1) a tectonic environment in which there is minimum hazard of increasing the mobility of the waste, increasing the rate of dissolution of waste, or increasing the rate of travel of waste from the repository; (2) a host medium of low permeability in the saturated zone or a host medium in an environment that limits accessibility of moisture to the waste in the unsaturated zone; (3) rocks with significant sorptive capacity for radionuclides; and (4) a flow system with long traveltime from the repository to the accessible environment

On risk assessment of high level radioactive waste disposal

International Nuclear Information System (INIS)

Smith, C.F.; Kastenberg, W.E.

1976-01-01

One of the major concerns with the continued growth of the nuclear power industry is the production of the high level radioactive wastes. The risks associated with the disposal of these wastes derives from the potential for release of radioactive materials into the environment. The development of a methodology for risk analysis is carried out. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. In the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected 35 year nuclear power program is determined. An index of relative nuclide hazard appropriate to problems involving the management of high level radioactive wastes is developed. As an illustration of the methodology, risk analyses are made for two proposed methods for waste management: extraterrestrial disposal and interim surface storage. The results of these analyses indicate that, within the assumptions used, the risks of these management schemes are small compared with natural background radiation doses. (Auth.)

Experimental synthesis of crystalline matrices based on Ce, Ba, Sr zirconates for immobilization of high-level radioactive actinides

International Nuclear Information System (INIS)

Anderson, E.B.; Burakov, B.E.; Vasiliev, V.G.; Starchenko, V.A.

1993-01-01

In geological disposal of high-level radioactive waste the main storage barriers, in the first place the matrix containing radionuclides, must remain undestructible over a long period of time. Very high requirements are imposed for the matrices from the viewpoint of their chemical stability and mechanical strength. Zirconates may be classified among compounds potentially suitable for the creation of crystalline matrices incorporating radionuclides in their structure. The paper considers results of laboratory experiments on the synthesis of crystalline matrices based on various zirconates by the methods of gas-static and axial pressing. Problems are discussed concerning the crystalline matrix industrial synthesis technology developed at the Radium Institute. One of the most promising directions in solving the problem of high-level waste (HLW) removal from the sphere of human activity is disposal in deep geological formations. The realization of this direction envisages creation of multibarrier compositions. Special attention is paid to the technology for the synthesis of the first, the most crucial, engineering barrier: the matrix into which radionuclides are incorporated. It is assumed that crystalline compounds best satisfy all the requirements as the most thermodynamically stable

Basic investigation and analysis for preferred host rocks and natural analogue study area with reference to high level radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Seo, Jeong Ryul; Park, J. K.; Hwang, D. H.; Lee, J. H.; Yun, H. S.; Kim, D. Y.; Park, H. S.; Koo, S. B.; Cho, J. D.; Kim, K. E. [Korea Inst. of Geology, Mining and Materials, Taejon (Korea, Republic of)

1997-12-01

The purpose of this study is basic investigation and analysis for preferred host rocks and natural analogue study area to develope underground disposal technique of high level radioactive waste in future. The study has been done for the crystalline rocks(especially granitic rocks) with emphasis of abandoned metallic mines and uranium ore deposits, and for the geological structure study by using gravity and aeromagnetic data. 138 refs., 54 tabs., 130 figs. (author)

Considering timescales in the post-closure safety of geological disposal of radioactive waste

International Nuclear Information System (INIS)

2009-01-01

A key challenge in the development of safety cases for the deep geological disposal of radioactive waste is handling the long time frame over which the radioactive waste remains hazardous. The intrinsic hazard of the waste decreases with time, but some hazard remains for extremely long periods. Safety cases for geological disposal typically address performance and protection for thousands to millions of years into the future. Over such periods, a wide range of events and processes operating over many different timescales may impact on a repository and its environment. Uncertainties in the predictability of such factors increase with time, making it increasingly difficult to provide definite assurances of a repository's performance and the protection it may provide over longer timescales. Timescales, the level of protection and the assurance of safety are all linked. Approaches to handling timescales for the geological disposal of radioactive waste are influenced by ethical principles, the evolution of the hazard over time, uncertainties in the evolution of the disposal system (and how these uncertainties themselves evolve) and the stability and predictability of the geological environment. Conversely, the approach to handling timescales can affect aspects of repository planning and implementation including regulatory requirements, siting decisions, repository design, the development and presentation of safety cases and the planning of pre- and post-closure institutional controls such as monitoring requirements. This is an area still under discussion among NEA member countries. This report reviews the current status and ongoing discussions of this issue. (author)

The Centralized Temporary Storage (ATC) Spanish. General and operational readiness in the management of high level radioactive waste

International Nuclear Information System (INIS)

Reyes, S.; Diaz, A.; Dilla, A.; Gonzalez, J. R.; Haro, R.

2014-01-01

The high-level waste will go to Centralized Temporary Storage (ATC) in Villar de Canas (Cuenca), which is the solution to your management until finished designing its final disposal in the Deep Geological Storage (AGP). Transport containers of high activity radioactive waste will be stored on arrival at the ATC. In time of management, waste will be taken remotely, will be encapsulated in secure conditions and stored in vaults designed to be cooled by natural convection of air confinement. The buildings in the facility will have a general provision optimize the movement of packages and people for the development of all these activities. (Author)

Reversibility and retrievability in geologic disposal of radioactive waste. A new Nea report

International Nuclear Information System (INIS)

Brown, P.A.; Pascatore, C.; Sumerling, T.

2001-01-01

Radioactive waste needs to be managed responsibly to ensure public safety and the protection of the environment, as well as security from unauthorized interference, now and in the future. One of the most challenging tasks is the management of long-lived radioactive waste that must be isolated from the human environment for many thousands, or even hundreds of thousands, of years. There is a consensus among the engaged technical community that engineered geologic disposal provides a safe and ethical method for the long term management of such waste. This method is also cited in the national policies of several countries as either a promising or appropriate method for dealing with long-lived radioactive waste. Engineered geologic disposal means emplacement of waste in repositories constructed deep underground in suitable geologic media. Thus the waste is contained, and safety assured by passive barriers with multiple safety functions, so that there is no need for any further actions by future generations. Primary principles of the engineered geologic disposal concept are that waste will only be emplaced in a repository when there is high confidence in the ultimate long-term safety, and that the long-term safety must not rely on actions following the closure of the repository. This does not mean, however, that actions cannot be taken. Most repository development programmes include the possibility of post-closure activities for security and monitoring purposes. (authors)

Application of remote sensing technique to site selection for low and intermediate level radioactive waste

International Nuclear Information System (INIS)

Chen Zhangru; Jin Yuanxin; Liu Yuemiao; Hou Dewen

2001-01-01

Based on the relative criteria of selection of disposal site for low and intermediate level radioactive waste, the social-economic conditions, landform, morphologic properties, regional geological stability, hydrogeological and engineering geological characters of adjacent area of Anhui, Zhejiang and Jiangsu provinces were investigated. The geological interpretation of thematic mapper images, field reconnaissance and data analysis were conducted during the research work. The results show that three areas in the west part of Zhejiang Province were recommended as potential site for disposal of low and intermediate level radioactive waste. They are Bajiaotang area, Tiebanchong area and Changxing-Guangde-Anji nabes

Characteristics of high-level radioactive waste forms for their disposal

International Nuclear Information System (INIS)

Kim, Seung Soo; Chun, Kwan Sik; Kang, Chul Hyung

2000-12-01

In order to develop a deep geological repository for a high-level radioactive waste coming from reprocessing of spent nuclear fuels discharged from our domestic nuclear power plants, the the required characteristics of waste form are dependent upon a solidifying medium and the amount of waste loading in the medium. And so, by the comparative analysis of the characteristics of various waste forms developed up to the present, a suitable medium is recommended.The overall characteristics of the latter is much better than those of the former, but the change of the properties due to an amorphysation by radiation exposure and its thermal expansion has not been clearly identified yet. And its process has not been commercialized. However, the overall properties of the borosilicate glass waste forms are acceptable for their disposal, their production cost is reasonable and their processes have already been commercialized. And plenty informations of their characteristics and operational experiences have been accumulated. Consequently, it is recommended that a suitable medium solidifying the HLW is a borosilicate glass and its composition for the identification of a reference waste form would be based on the glass frit of R7T7

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

Neotectonic movement feature in preselection area for high level radioactive waste repository

International Nuclear Information System (INIS)

Huang Xianfang; Gao Yang; He Jianguo; Li Jianzhong; Gao Honglei; Xu Guoqing

2010-01-01

Neotectonic activity intensity is an important criteria for evaluating high level radioactive waste repository. The guiding ideology, methods and application of neotectonic study are elaborated in the paper. According to comparison research between the south and north part of east Tianshan area, the south part of east Tianshan is regarded as relative stable or relative weak in neotectonic movement in Neogene period and was selected as preselection area for high level radioactive waste repository. (authors)

Nuclear Regulatory Commission staff development of the license application review plan for a high-level radioactive waste repository

International Nuclear Information System (INIS)

Johnson, R.L.; Holonich, J.J.; Lee, M.P.; Delligatti, M.S.

1993-01-01

The Nuclear Regulatory Commission staff has recently started a new initiative to develop the License Application Review Plan (LARP) which the staff will use in its reviews of the U.S. Department of Energy's (DOE's) license application (LA) for a geologic repository for the disposal of high-level radioactive waste (HLW). This paper describes the staff's approach for developing the LARP, the development schedule and current status, the organization and content of the LARP, and the staff's LA review strategy. Therefore, it gives a preview of the draft LARP which will be made available in late 1993. It also describes how the LARP will be used as guidance to the staff in conducting reviews of regulatory and technical issues important to the licensing of a geologic repository. Finally, the benefits to the NRC staff, DOE, and other parties are discussed

Geochemistry of actinides. Application to the storage of high level radioactive wastes. Under the supervision of Mr Michel Treuil

International Nuclear Information System (INIS)

Bouabdallah, Noureddine; Cunault, Jean-Baptiste; Houtin, Gwenaelle; Leborgne, Francois; Lemaire, Celine; Lemarchand, Damien; Quitte, Ghylaine

1997-06-01

This collective research report first addresses the chemistry of actinides with a description of their atomic orbitals and the study of their behaviour in solution. The author addresses several aspects: historical overview on actinides, radioactivity, chemical reactions in aqueous solution, redox chemistry, speciation in solution with respect to water characteristics in deep storage conditions. The second part gathers several studies performed on a natural laboratory (the Oklo site in which nuclear reactions occurred about 2 billions years ago) and reports the modelling of radionuclide transfer within a geological system (the model is applied to the Oklo site). The third part addresses issues related to the nuclear fuel cycle, and the storage modes and materials envisaged and involved regarding the storage of high level radioactive wastes, notably in France

Study on the high level radioactive wastes geological isolation seen from the social acceptance of science and technology. (2) Point that installs choices in explanation to the another field specialist

International Nuclear Information System (INIS)

Wada, Ryutaro; Tanaka, Satoru; Nagasaki, Shinya

2010-01-01

Generally speaking, a vast, advanced and unfamiliar science and technology which has the potential hazard, is unacceptable by public for the fear of its unknown nature. The siting problem of geological disposal for high level radioactive wastes is one of the typical examples. There is only one disposal concept in Japan now. However, there might be a lot of choices because it can be promoted greater understanding by comparative study. This study examined the point that installed appropriate choices to explain in specialists in another field etc. other than the nuclear backend field. At first, this study surveyed the part where recognition and understanding of the safety when disposing of high level radioactive wastes (HLW) were not able to be shared by the discussion between specialists before. As a result, it has been understood that it is the evaluation etc. part which are 'Disposal scenario and safety evaluation result' and 'Forecast of a technology concerned in the future'. Therefore, it seems as the position and the region of the evaluation etc. good to install these choices. Moreover, the form of choices seems to be good two or more disposal concepts that cost and safety are evaluated on one candidate site. In addition, it seems that these choices are used and it is good for 'Specialists other than the nuclear power back end to which the range in the field made a specialty has adjusted' at the academic society etc. to repeat the explanation and the discussion. (author)

Temperature distributions in a salt formation used for the ultimate disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Ploumen, P.

1980-01-01

In the Federal Republic of Germany the works on waste disposal is focussed on the utilization of a salt formation for ultimate disposal of radioactive wastes. Heat released from the high-level waste will be dissipated in the salt and the surrounding geologic formations. The occuring temperature distributions will be calculated with computer codes. A survey of the developed computer codes will be shown; the results for a selected example, taking into account the loading sequence of the waste, the mine ventilation as well as an air gap between the waste and the salt, will be discussed. Furthermore it will be shown that by varying the disposal parameters, the maximum salt temperature can be below any described value. (Auth.)

High level radioactive waste management facility design criteria

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1993-01-01

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding

Draft directive on the management of radioactive wastes based on deep geological disposal

International Nuclear Information System (INIS)

Anon.

2010-01-01

The European Commission works on a legal framework to assure that all the member states apply the same standards in all the stages of the management of spent fuels and radioactive wastes till their definitive disposal. The draft propositions are the following. The standards to follow are those proposed by the IAEA. First, each member state has to set a national program dedicated to the management of radioactive wastes. This program will have to detail: the chosen solution, the description of the project, a time schedule, costs and financing. Secondly, the exportation of nuclear wastes for definitive disposal is not allowed unless the 2 countries have agreed to build a common nuclear waste disposal center. Thirdly, the population will have to be informed on the project and will have to take part in the decision process. Fourthly, the standards set by IAEA will be enforced by law. There is a broad consensus between scientists and international organizations like IAEA to consider that the disposal in deep geological layers of high-level radioactive wastes is the most adequate solution. (A.C.)

Managing commercial high-level radioactive waste: summary

International Nuclear Information System (INIS)

1982-04-01

This summary presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste - an issue that has been debated over the last decade and that now appears to be moving toward major congressional action. After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue. The continued lack of final isolation facilities has raised two key problems that underlie debates about radioactive waste policy. First, some question the continued use of nuclear power until it is shown that safe final isolation for the resulting wastes can and will be accomplished, and argue that the failure to develop final isolation facilities is evidence that it may be an insoluble problem. Second, because there are no reprocessing facilities or federal waste isolation facilities to accept spent fuel, existing reactors are running out of spent fuel storage space, and by 1986 some may face a risk of shutting down for some period. Most of the 72,000 metric tons of spent fuel expected to be generated by the year 2000 will still be in temporary storage at that time. While it is possible that utilities could provide all necessary additional storage at reactor sites before existing basins are filled, some supplemental storage may be needed if there are delays in their efforts

Vitrification of high-level radioactive and hazardous wastes

International Nuclear Information System (INIS)

Lutze, W.

1993-12-01

The main objective is to summarize work conducted on glasses as waste forms for high-level radioactive fission product solutions up to the late 1980's (section I and II). Section III addresses the question, whether waste forms designed for the immobilization of radioactive residues can be used for the same purpose for hazardous wastes. Of particular interest are those types of hazardous wastes, e.g., fly ashes from municipal combustion plants, easy to convert into glasses or ceramic materials. A large number of base glass compositions has been studied to vitrify waste from reprocessing but only borosilicate glasses with melting temperatures between 1100 C and 1200 C and very good hydrolytic stability is used today. (orig./HP) [de

Self-sealing of Fractures in Argillaceous Formations in the Context of Geological Disposal of Radioactive Waste

International Nuclear Information System (INIS)

2010-01-01

Disposal of high-level radioactive waste and spent nuclear fuel in engineered facilities, or repositories, located deep underground in suitable geological formations is being developed worldwide as the reference solution to protect humans and the environment both now and in the future. Assessing the long-term safety of geological disposal requires developing a comprehensive understanding of the geological environment. The transport pathways are key to this understanding. Of particular interest are fractures in the host rock, which may be either naturally occurring or induced, for example, during the construction of engineered portions of a repository. Such fractures could provide pathways for migration of contaminants. In argillaceous (clay) formations, there is evidence that, over time, fractures can become less conductive and eventually hydraulically insignificant. This process is commonly termed 'self-sealing'. The capacity for self-sealing relates directly to the function of clay host rocks as migration barriers and, consequently, to the safety of deep repositories in those geological settings. This report - conducted under the auspices of the NEA Clay Club - reviews the evidence and mechanisms for self-sealing properties of clays and evaluates their relevance to geological disposal. Results from laboratory tests, field investigations and geological analogues are considered. The evidence shows that, for many types of argillaceous formations, the understanding of self-sealing has progressed to a level that could justify its inclusion in performance assessments for geological repositories. (authors)

Exposing the faults: the geological case against the plans by UK NIREX to dispose of radioactive waste

International Nuclear Information System (INIS)

Richardson, P.J.

1989-01-01

NIREX has given the strong impression throughout is recent public consultation exercise connected with underground disposal of low and intermediate level waste that the problem is one of public and political acceptability, rather than one of a technical nature. This is not the place in which to list the considerable failings of this latest attempt. Nevertheless, the results of the consultation process show quite clearly that it has no mandate from the British public to develop a single, national deep repository for the burial of radioactive waste. There is considerable opposition to this method of managing radioactive waste and a quite reasonable suspicion of the claims by NIREX concerning the supposed integrity and safety of this deep burial option. This report gives substance to those suspicions and spells out in detail the significant areas of uncertainty in the concept of effective geological containment of hazardous radioactive elements, which remain dangerous for tens of thousands of years. Because the science of geology is essentially retrospective rather than predictive, NIREX's plans for a single, national, deep 'repository' depend heavily upon a wide range of assumptions about the geological and hydrogeological regimes in certain areas of the United Kingdom (UK). This report demonstrates that these assumptions are based on a limited understanding of UK geology and on unvalidated and simplistic theoretical models of geological processes, the performance of which can never be directly tested over the long time-scales involved. An extensive public relations exercise cannot hide the unavoidable technical uncertainties associated with burying radioactive waste. Dumping radioactive waste is foolhardy and irresponsible in the face of these unknowns. NIREX's proposals offer no guarantees for the safe and effective containment of radioactivity. They are deeply flawed. This report exposes the faults. (author)

Reducing the likelihood of future human activities that could affect geologic high-level waste repositories

International Nuclear Information System (INIS)

1984-05-01

The disposal of radioactive wastes in deep geologic formations provides a means of isolating the waste from people until the radioactivity has decayed to safe levels. However, isolating people from the wastes is a different problem, since we do not know what the future condition of society will be. The Human Interference Task Force was convened by the US Department of Energy to determine whether reasonable means exist (or could be developed) to reduce the likelihood of future human unintentionally intruding on radioactive waste isolation systems. The task force concluded that significant reductions in the likelihood of human interference could be achieved, for perhaps thousands of years into the future, if appropriate steps are taken to communicate the existence of the repository. Consequently, for two years the task force directed most of its study toward the area of long-term communication. Methods are discussed for achieving long-term communication by using permanent markers and widely disseminated records, with various steps taken to provide multiple levels of protection against loss, destruction, and major language/societal changes. Also developed is the concept of a universal symbol to denote Caution - Biohazardous Waste Buried Here. If used for the thousands of non-radioactive biohazardous waste sites in this country alone, a symbol could transcend generations and language changes, thereby vastly improving the likelihood of successful isolation of all buried biohazardous wastes

Reducing the likelihood of future human activities that could affect geologic high-level waste repositories

Energy Technology Data Exchange (ETDEWEB)

1984-05-01

The disposal of radioactive wastes in deep geologic formations provides a means of isolating the waste from people until the radioactivity has decayed to safe levels. However, isolating people from the wastes is a different problem, since we do not know what the future condition of society will be. The Human Interference Task Force was convened by the US Department of Energy to determine whether reasonable means exist (or could be developed) to reduce the likelihood of future human unintentionally intruding on radioactive waste isolation systems. The task force concluded that significant reductions in the likelihood of human interference could be achieved, for perhaps thousands of years into the future, if appropriate steps are taken to communicate the existence of the repository. Consequently, for two years the task force directed most of its study toward the area of long-term communication. Methods are discussed for achieving long-term communication by using permanent markers and widely disseminated records, with various steps taken to provide multiple levels of protection against loss, destruction, and major language/societal changes. Also developed is the concept of a universal symbol to denote Caution - Biohazardous Waste Buried Here. If used for the thousands of non-radioactive biohazardous waste sites in this country alone, a symbol could transcend generations and language changes, thereby vastly improving the likelihood of successful isolation of all buried biohazardous wastes.

Suggestions on R and D work of high-level radioactive waste disposal in China

International Nuclear Information System (INIS)

Xu Guoqing

2012-01-01

The difference between repository and generic underground facilities is described. Some differences and similarities of site selection between the low and medium radioactive waste disposal, nuclear power station and high-level radioactive waste repository are also discussed here. We trend to extremely emphasize the safety of high-level radioactive waste disposal because of high toxicity, long half-life and long safety disposal period of this kind of radioactive wastes; because radioactive waste in the repository is of high specific activities and buried in depth, it would be difficult to meddle with its safety. In case of repository system being destroyed, the author considers that in the stages of regional and area site selection, the first task is to investigate regional tectonic stability. Some problems about disposal options and others are also discussed in this paper. (author)

Hydrological performance assessment on siting the high level radioactive waste repository

International Nuclear Information System (INIS)

Guo Yonghai; Liu Shufen; Wang Ju; Wang Zhiming; Su Rui; Lv Chuanhe; Zong Zihua

2007-01-01

Based on the research experiences in China and some developed countries in the world, the processes and methods on hydrological performance assessment for the siting of high radioactive repository are discussed in this paper. The methods and contents of hydrological performance assessment are discussed respectively for region, area and site hydrological investigation stages. At the same time, the hydrological performance assessment of the potential site for high level radioactive waste in China is introduced. (authors)

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)

Midwestern High-Level Radioactive Waste Transportation Project

International Nuclear Information System (INIS)

1993-01-01

On February 17,1989, the Midwestern Office of The Council of State Governments and the US Department of Energy entered into a cooperative agreement authorizing the initiation of the Midwestern High-Level Radioactive Waste Transportation Project. The transportation project continued to receive funding from DOE through amendments to the original cooperative agreement, with December 31, 1993, marking the end of the initial 5-year period. This progress report reflects the work completed by the Midwestern Office from February 17,1989, through December 31,1993. In accordance with the scopes of work governing the period covered by this report, the Midwestern Office of The Council of State Governments has worked closely with the Midwestern High-Level Radioactive Waste Committee. Project staff have facilitated all eight of the committee's meetings and have represented the committee at meetings of DOE's Transportation Coordination Group (TCG) and Transportation External Coordination Working Group (TEC/WG). Staff have also prepared and submitted comments on DOE activities on behalf of the committee. In addition to working with the committee, project staff have prepared and distributed 20 reports, including some revised reports (see Attachment 1). Staff have also developed a library of reference materials for the benefit of committee members, state officials, and other interested parties. To publicize the library, and to make it more accessible to potential users, project staff have prepared and distributed regular notices of resource availability

Assessment of Deep Geological Environmental Condition for HLW Disposal in Korea

International Nuclear Information System (INIS)

Koh, Yong Kweon; Bae, Dae Seok; Kim, Kyung Su

2010-04-01

The research developed methods to study and evaluate geological factors and items to select radioactive waste disposal site, which should meet the safety requirements for radioactive waste disposal repositories according to the guidelines recommended by IAEA. A basic concept of site evaluation and selection for high level radioactive waste disposal and develop systematic geological data management with geological data system which will be used for site selection in future are provided. We selected 36 volcanic rock sites and 26 gneissic sites as the alternative host rocks for high level radioactive waste disposal and the geochemical characteristics of groundwaters of the four representative sites were statistically analyzed. From the hydrogeological and geochemical investigation, the spatial distribution characteristics were provided for the disposal system development and preliminary safety assessment. Finally, the technology and scientific methods were developed to obtain accurate data on the hydrogeological and geochemical characteristics of the deep geological environments

Risk assessments for the disposal of high level radioactive wastes

International Nuclear Information System (INIS)

Smith, C.F.

1975-01-01

The risks associated with the disposal of high level wastes derive from the potential for release of radioactive materials into the environment. The assessment of these risks requires a methodology for risk analysis, an identification of the radioactive sources, and a method by which to express the relative hazard of the various radionuclides that comprise the high level waste. The development of a methodology for risk analysis is carried out after a review of previous work in the area of probabilistic risk assessment. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. At the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected thirty-five year nuclear power program is determined

The use of scientific and technical results from underground research laboratory investigations for the geological disposal of radioactive waste

International Nuclear Information System (INIS)

2001-09-01

The objective of the report is to provide information on the use of results obtained from underground research laboratory investigations for the development of a deep geological repository system for long lived and/or high level radioactive waste including spent fuel. Specifically, it should provide Member States that intend to start development of a geological disposal system with an overview of existing facilities and of the sorts and quality of results that have already been acquired. The report is structured into six main themes: rock characterization methodologies and testing; assessment of the geological barrier; assessment of the engineered barrier system; respository construction techniques; demonstration of repository operations; confidence building and international co-operation

Vitrification treatment options for disposal of greater-than-Class-C low-level waste in a deep geologic repository

International Nuclear Information System (INIS)

Fullmer, K.S.; Fish, L.W.; Fischer, D.K.

1994-11-01

The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE's investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4)

Remote ignitability analysis of high-level radioactive waste

International Nuclear Information System (INIS)

Lundholm, C.W.; Morgan, J.M.; Shurtliff, R.M.; Trejo, L.E.

1992-09-01

The Idaho Chemical Processing Plant (ICPP), was used to reprocess nuclear fuel from government owned reactors to recover the unused uranium-235. These processes generated highly radioactive liquid wastes which are stored in large underground tanks prior to being calcined into a granular solid. The Resource Conservation and Recovery Act (RCRA) and state/federal clean air statutes require waste characterization of these high level radioactive wastes for regulatory permitting and waste treatment purposes. The determination of the characteristic of ignitability is part of the required analyses prior to calcination and waste treatment. To perform this analysis in a radiologically safe manner, a remoted instrument was needed. The remote ignitability Method and Instrument will meet the 60 deg. C. requirement as prescribed for the ignitability in method 1020 of SW-846. The method for remote use will be equivalent to method 1020 of SW-846

On selection of geological medium for disposal of high-level radwaste

International Nuclear Information System (INIS)

Min Maozhong

1991-01-01

The present paper briefly reviews the suitability of some rocks as geological disposal repositories of high-level radwaste (HLW). The suitable rocks for geological ogi disposal of HLW are rock salt (salt diapir, bedded salt), granite, argillaceous rocks, tuff, basalt, gabbro, diabase, anhydrite, marine sedimentary rocks etc., especially, rock salt, granite, and argillaceous rocks. The data of principal hydraulic properties, mechanical-physical properties for various rocks in typical environment which might be considered for disposal purposes are also given in this paper. These data give a reference to China's geological disposal of HLW in the future

Strategies for high-level radioactive waste management: the U.S. experience

International Nuclear Information System (INIS)

Cotton, T.A.

1984-01-01

Technology exists or is under development for the safe, retrievable storage of spent fuel from commercial nuclear reactors and high-level waste from reprocessing that fuel, for many decades, and no insuperable scientific obstacles to permanent disposal of spent fuel or high-level waste in geologic repositories have been identified. However, there are significant institutional obstacles to developing such repositories: strong local opposition to siting and the requirement for a sustained commitment of money and skilled manpower over a period of decades. These create strong incentives to defer the political and economic costs of developing disposal facilities by using less expensive interim storage; yet continued deferral may affect the acceptability of nuclear power. Thus the principal strategic policy issue in high-level waste management is how rapidly to develop disposal facilities. Some countries plan decades of storage before choosing a repository site or a disposal technology, while the United States has enacted a law requiring operation of a geologic repository by 1998. This paper discusses waste management strategic issues and major provisions of the U.S. law, emphasizing those measures dealing with the institutional obstacles to developing geologic repositories. (author)

An International Peer Review of the Programme for the Deep Geological Disposal of High Level Radioactive Waste from Pyro-Processing in the Republic of Korea. Report of an IAEA International Review Team

International Nuclear Information System (INIS)

2013-09-01

The development of a radioactive waste disposal system is indispensable in maintaining the sustainability of nuclear energy. The Korea Atomic Energy Research Institute (KAERI) has studied the direct geological disposal of spent nuclear fuel since 1997. KAERI has also focused on the development of processes suitable for reducing the volume of spent nuclear fuel and the recycling of valuable fissile material. One of the most promising technologies investigated by KAERI is the pyro-processing of spent nuclear fuel followed by the geological disposal of the generated high level waste (HLW). Since 2007, KAERI has been running a research programme focusing on the recycling of spent nuclear fuel, as well as studies aimed at the development of a relevant geological disposal system able to accept the resulting HLW. The core aims of the KAERI study were to characterize the geological media, design a repository system and assess the overall safety of the disposal system. The development of pyro-processing technology is ongoing and has not yet been demonstrated at the commercial level. Thus, the government of the Republic of Korea requested an assessment of the technical feasibility of this technology. The assessment also included the appraisal of a disposal solution for waste generated by pyro-processing. With regard to the latter, KAERI requested that the IAEA review the status of the disposal project within the Waste Management Assessment and Technical Review Programme (WATRP). Peer reviews are increasingly being acknowledged as an important element in building broader stakeholder confidence in the safety and viability of related facilities. This report presents the consensus view of the international group of experts convened by the IAEA to perform the review

Reversibility and switching options values in the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Ionescu, Oana; Spaeter, Sandrine

2011-07-01

This article offers some economic insights for the debate on the reversible geological disposal of radioactive waste. Irreversibility due to large sunk costs, an important degree of flexibility and several sources of uncertainty are taken into account in the decision process relative to the radioactive waste disposal. We draw up a stochastic model in a continuous time framework to study the decision problem of a reversible repository project for the radioactive waste, with multiple disposal stages. We consider that the value of reversibility, related to the radioactive waste packages, is jointly affected by economic and technological uncertainty. These uncertainties are modeled, first, by a 2-Dimensional Geometric Brownian Motion, and, second, by a Geometric Brownian Motion with a Poisson jump process. A numerical analysis and a sensitivity study of various parameters are also proposed. Switching options values in the geological disposal of radioactive waste. (authors)

Alternatives for long-term management of defense high-level radioactive waste, Hanford Reservations, Richland, Washington

International Nuclear Information System (INIS)

1977-09-01

The objective of this document is to provide information or alternatives that are being considered for the long-term management of defense high-level radioactive waste stored at Hanford in underground tanks and in stainless steel-lined concrete basins. For purposes of basic programmatic decision making, four major alternatives based on disposal location are considered. The steps leading to placement of the waste in the following locations are illustrated: existing waste tanks; onsite engineered surface facilities; onsite geologic repository; and offsite geologic repository. The four major disposal alternatives are expanded into 27 alternative plans by considering: (1) variations in the final form of the high-level fraction (with radionuclide removal) to include glass, concrete, and powder; (2) variations in the final form of the dehydrated waste product to include glass, calcined clay, and powder; and (3) variations in the treatment and handling of encapsulated waste to include packaging of capsules in canisters and conversion of the strontium fluoride and cesium chloride to glass; canisters stored in sealed casks on the surface are disposed of in a surface vault after the radionuclides have decayed sufficiently to avoid a heat-transfer problem. A description of the technology, a preliminary risk assessment, and preliminary cost estimates for each of these 27 plans are presented. The technology required to implement any of the 27 alternative plans has not been developed to the point where any plan can be considered completely technically sound and feasible

Viewpoint of defining the groundwater chemistry for the performance assessment on geological disposal of high level radioactive waste

International Nuclear Information System (INIS)

Sasamoto, Hiroshi; Yui, Mikazu

2000-01-01

This report presents the viewpoint of defining the groundwater chemistry for performance assessment of the second progress report for research and development on geological disposal. Based on the results of statistical analysis (binary scatter plots) of the measured data in addition to the consideration of the first progress report, we defined the five hypothetically modeled groundwaters considering the general geological conditions and importance for performance assessment. In order to evaluate the priority of groundwater chemistries, we have analyzed the above five hypothetical groundwaters by considering the results of multivariate statistical analyses, data reliability, evidence for geochemical controls on groundwater chemistry and exclusion criteria for potential repository sites in Japan. As a result, the fresh reducing high pH (FRHP) type groundwater has been selected for the Reference Case analysis, and the saline reducing high pH (SRHP) type groundwater has been selected for the Alternative Geological Environmental Case analysis, respectively. (author)

Technical issues in the geologic disposal of radioactive wastes

International Nuclear Information System (INIS)

Weart, W.D.

1980-01-01

The status of technical understanding regarding radioactive waste repositories in geologic media is improving at a rapid rate. Within a few years the knowledge regarding non-salt repositories will be on a par with that which now exists for salt. To date there is no technical reason to doubt that geologic repositories in several different geologic media can be safely implemented to provide long-term isolation of radioactive wastes. Indeed, for bedded salt, there is now sufficient knowledge to allow all the identified phenomena to be bounded with satisfactory resultant consequences. It is possible to now proceed with technical confidence in an orderly development of a bedded-salt repository at a satisfactory site. This development would call for in-situ experiments, at the earliest possible stage, to confirm or validate the predictions made for the site. These in-situ experiments will be necessary for each repository in a different rock type. If, for non-technical reasons, repository development is delayed, field test facilities should be located as soon as possible in geologic settings typical of proposed repositories. Extensive testing to resolve generic issues will allow subsequent development of repositories to proceed more rapidly with only minimal in-situ testing required to resolve site-specific concerns

Management of high level radioactive waste

International Nuclear Information System (INIS)

Redon, A.; Mamelle, J.; Chambon, M.

1977-01-01

The world wide needs in reprocessing will reach the value of 10.000 t/y of irradiated fuels, in the mid of the 80's. Several countries will have planned, in their nuclear programme, the construction of reprocessing plants with a 1500 t/y capacity, corresponding to 50.000 MWe installed. At such a level, the solidification of the radioactive waste will become imperative. For this reason, all efforts, in France, have been directed towards the realization of industrial plants able of solidifying the fission products as a glassy material. The advantages of this decision, and the reasons for it are presented. The continuing development work, and the conditions and methods of storing the high-level wastes prior to solidification, and of the interim storage (for thermal decay) and the ultimate disposal after solidification are described [fr

Fundamental problem of high-level radioactive waste disposal policy in Japan. Critical analysis responding to the publication of 'Nationwide Map of Scientific Features for Geological Disposal' by the Japanese government

International Nuclear Information System (INIS)

Juraku, Kohta

2017-01-01

The government explains that 'Scientific Characteristic Map' (hereinafter 'Map') shows the scientific characteristics of sites that are thought necessary to be taken into account when choosing the place to implement geological disposal and their geographical distribution on the Japanese map for the convenience to 'roughly overlook.' Nuclear Waste Management Organization of Japan (NUMO) as the implementing agency for geological disposal and the government (Agency for Natural Resources and Energy of Ministry of Economy, Trade and Industry) stress that this Map does not indicate so-called 'optimum land,' but it is the 'first step of a long way to realize disposal' for high-level radioactive waste (HLW). However, there clearly lurks a debate about the acceptance of the location of geological disposal in the future. The author has pointed out that the essence of the HLW disposal problem is a problem of 'value selection' that should be decided prior to the location of disposal site. The author believes that it is the competence of society how to identify the path of countermeasures by reconciling in a high degree the justice of the policies supported by scientific and professional knowledge and the justice of social decision making through a democratic duty process. However, the government is trying to forward HLW disposal only from the viewpoint of location problems, while neglecting the problem of 'value selection.' (A.O.)

Bacterial Diversity in Bentonites, Engineered Barrier for Deep Geological Disposal of Radioactive Wastes.

Science.gov (United States)

Lopez-Fernandez, Margarita; Cherkouk, Andrea; Vilchez-Vargas, Ramiro; Jauregui, Ruy; Pieper, Dietmar; Boon, Nico; Sanchez-Castro, Ivan; Merroun, Mohamed L

2015-11-01

The long-term disposal of radioactive wastes in a deep geological repository is the accepted international solution for the treatment and management of these special residues. The microbial community of the selected host rocks and engineered barriers for the deep geological repository may affect the performance and the safety of the radioactive waste disposal. In this work, the bacterial population of bentonite formations of Almeria (Spain), selected as a reference material for bentonite-engineered barriers in the disposal of radioactive wastes, was studied. 16S ribosomal RNA (rRNA) gene-based approaches were used to study the bacterial community of the bentonite samples by traditional clone libraries and Illumina sequencing. Using both techniques, the bacterial diversity analysis revealed similar results, with phylotypes belonging to 14 different bacterial phyla: Acidobacteria, Actinobacteria, Armatimonadetes, Bacteroidetes, Chloroflexi, Cyanobacteria, Deinococcus-Thermus, Firmicutes, Gemmatimonadetes, Planctomycetes, Proteobacteria, Nitrospirae, Verrucomicrobia and an unknown phylum. The dominant groups of the community were represented by Proteobacteria and Bacteroidetes. A high diversity was found in three of the studied samples. However, two samples were less diverse and dominated by Betaproteobacteria.

Geology Of Wadi Sidri Radioactive Ocurrences, Western Sinai, Egypt

OpenAIRE

El Kassas, I. A. [ابراهيم علي القصاص

1995-01-01

Geologic and radiomclric investigations have been carried out in the environs of Wadi Sidri in Western Sinai, applying a combination of various geological, geophysical and gcochcmical techniques. This work revealed the presence of some radioactive anomalies of various intensities, extensions and origin, associated with different rock types. The discovered anomalies arc classified into two main groups of quite different types but they seem to be genetically related to each other. The first typ...

Shale disposal of U.S. high-level radioactive waste.

Energy Technology Data Exchange (ETDEWEB)

Sassani, David Carl; Stone, Charles Michael; Hansen, Francis D.; Hardin, Ernest L.; Dewers, Thomas A.; Martinez, Mario J.; Rechard, Robert Paul; Sobolik, Steven Ronald; Freeze, Geoffrey A.; Cygan, Randall Timothy; Gaither, Katherine N.; Holland, John Francis; Brady, Patrick Vane

2010-05-01

This report evaluates the feasibility of high-level radioactive waste disposal in shale within the United States. The U.S. has many possible clay/shale/argillite basins with positive attributes for permanent disposal. Similar geologic formations have been extensively studied by international programs with largely positive results, over significant ranges of the most important material characteristics including permeability, rheology, and sorptive potential. This report is enabled by the advanced work of the international community to establish functional and operational requirements for disposal of a range of waste forms in shale media. We develop scoping performance analyses, based on the applicable features, events, and processes identified by international investigators, to support a generic conclusion regarding post-closure safety. Requisite assumptions for these analyses include waste characteristics, disposal concepts, and important properties of the geologic formation. We then apply lessons learned from Sandia experience on the Waste Isolation Pilot Project and the Yucca Mountain Project to develop a disposal strategy should a shale repository be considered as an alternative disposal pathway in the U.S. Disposal of high-level radioactive waste in suitable shale formations is attractive because the material is essentially impermeable and self-sealing, conditions are chemically reducing, and sorption tends to prevent radionuclide transport. Vertically and laterally extensive shale and clay formations exist in multiple locations in the contiguous 48 states. Thermal-hydrologic-mechanical calculations indicate that temperatures near emplaced waste packages can be maintained below boiling and will decay to within a few degrees of the ambient temperature within a few decades (or longer depending on the waste form). Construction effects, ventilation, and the thermal pulse will lead to clay dehydration and deformation, confined to an excavation disturbed zone within

Factors affecting the release of radioactivity to the biosphere during deep geologic disposal of radioactive solids through underground water

International Nuclear Information System (INIS)

Solomah, A.G.

1984-01-01

The chemical alteration formed by ground water on the solidified radioactive waste during deep geologic disposal represents the most likely mechanism by which dangerous radioactive species could be reintroduced into the biosphere. Knowing the geologic history of the repository, the chemistry of the ground water and the mechanisms involved in the corrosion of the radioactive solids can provide help to predict the long-term stability of these materials. The factors that must be considered in order to assess the safety and the risk associated with such a disposal strategy are presented. The leaching behavior of a solidified radioactive waste form called SYNROC-B (SYNthetic ROCks) is discussed. Different simulated ground water brines similar to those of the repository sites were prepared and used as the leaching media in leaching experiments

Radionuclide transport calculations from high-level long-lived radioactive waste disposal in deep clayey geologic formation toward adjacent aquifers

International Nuclear Information System (INIS)

Genty, A.; Le Potier, C.

2007-01-01

In the context of high-level nuclear waste repository safety calculations, the modeling of radionuclide migration is of first importance. Three dimensional radionuclide transport calculations in geological repository need to describe objects of the meter scale embedded in geologic layer formations of kilometer extension. A complete and refined spatial description would end up with at least meshes of hundreds of millions to billions elements. The resolution of this kind of problem is today not reachable with classical computers due to resources limitations. Although parallelized computation appears as potential tool to handle multi-scale calculations, to our knowledge no attempt have been yet performed. One emerging solution for repository safety calculations on very large cells meshes consists in using a domain decomposition approach linked to massive parallelized computer calculation. In this approach, the repository domain is divided in small elementary domains and transport calculation are performed independently on different processor for each elementary domain. Before to develop this possible solution, we performed some preliminary test in order to access the order of magnitude of cells needed to perform converged calculation on one elementary disposal domain and to check if Finite Volume (FV) based on Multi Point Flux Approximation (MPFA) spatial scheme or more classical Mixed Hybrid Finite Element (MHFE) spatial scheme were adapted for those calculations in highly heterogeneous porous media. Our preliminary results point out that MHFE and VF schemes applied on non-parallelepiped hexahedral cells for flow and transport calculations in highly heterogeneous media gave satisfactory results. Nevertheless further investigations and additional calculations are needed in order to exhibit the mesh discretization level needed to perform converged calculations. (authors)

Radioactive waste disposal in deep geologic deposits. Associated research problems

International Nuclear Information System (INIS)

Rousset, G.

1992-01-01

This paper describes the research associated problems for radioactive waste disposal in deep geologic deposits such granites, clays or salt deposits. After a brief description of the underground disposal, the author studies the rheology of sedimentary media and proposes rheological models applied to radioactive wastes repositories. Waste-rock interactions, particularly thermal effects and temperature distribution versus time. 17 refs., 14 figs

Southern routes for high-level radioactive waste: Agencies, contacts, and designations

International Nuclear Information System (INIS)

1991-05-01

The Southern Routes for High-Level Radioactive Waste: Agencies, Contacts and Designations is a compendium of sixteen southern states' routing programs for the transportation of high-level radioactive materials. The report identifies the state-designated routing agencies as defined under 49 Code of Federal Regulations (CFR) Part 171 and provides a reference to the source and scope of the agencies' rulemaking authority. Additionally, the state agency and contact designated by the state's governor to receive advance notification and shipment routing information under 10 CFR Parts 71 and 73 are also listed. This report also examines alternative route designations made by southern states and the lessons that were learned from the designation process

Natural phenomena with low probability and crustal movement on high level radioactive waste geological disposal

International Nuclear Information System (INIS)

Kusunose, Kinichiro; Sato, Takashi; Cho, Akio

1997-01-01

By forecast of Ministry of International Trade and Industry, total amount of glassification materials will attain to about 40,000 of can of 200 liter in 2050 year. A geological circumstance of geological disposal needs to be stable for long time (at least more than 10,000 years). By development of long-term prediction method of crusted movement, the experiments of fracture of granite sample under confining pressure of 100 MPa suggested that the physical properties were Young's modulus 68 GPa, Poisson's ratio 0.29, the maximum strength 731 MPa and pressure of beginning dilatancy 457 MPa. The rupture behavior of granite belongs to class II. Skewness of perimeter at the largest strength was about 1%. There are static and dynamic process in the rupture cross-section forming process. With developing an evaluation method of volcanic activities effects on the basis of study on the change of circumstances caused on the large eruption, the change of vegetation was proved in the large area by analysis of pollen. Ionium age determination measurement equipment have lower back ground level than that of γ-ray counter. Accordingly, it is useful for measurement of low concentration of them. (S.Y.)

Safe disposal of high-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Ringwood, A E [Australian National Univ., Canberra. Research School of Earth Sciences

1980-10-01

Current strategies in most countries favour the immobilisation of high-level radioactive wastes in borosilicate glasses, and their burial in large, centralised, mined repositories. Strong public opposition has been encountered because of concerns over safety and socio-political issues. The author develops a new disposal strategy, based on immobilisation of wastes in an extremely resistant ceramic, SYNROC, combined with burial in an array of widely dispersed, very deep drill holes. It is demonstrated that the difficulties encountered by conventional disposal strategies can be overcome by this new approach.

Low probability natural phenomena and crustal movement on high level radioactive waste geological disposal

International Nuclear Information System (INIS)

Kusunose, Kinichiro; Sato, Takashi; Cho, Akio; Togashi, Shigeko; Matsumoto, Akikazu; Kanai, Yutaka; Okumura, Koji; Shimokawa, Koichi; Mizuno, Kiyohide

1998-01-01

On subtheme ''development of long-term estimate method of crystal movement'', a control method has been developed under the conditions of 500 MPa confining pressure at 300degC. The method was tested under the conditions of 100 MPa confining pressure at room temperature and the rock fracture experiment was succeeded. On subtheme ''estimation method on the effect of volcanic activity'', in order to evaluate the effects of tephra fall on environment, pollen analysis of sample on outcrop in Sakaida and the topographic and geological survey of river terrace along Nyu-river in Yamagata prefecture were carried out. These results showed number of pollen was decreased immediately after AT tephra fall originated in Kyushu, so that effect of ash on forest was proved. However, the effect of AT tephra fall on ecological system was not so large as changing forest compositing species. On establishment of accurate geologic time measurement of pyroclastic materials, uranium and thorium were chemically separated from various kinds of mineral concentrated materials separated from pyroclastic materials. Iso chron of them was obtained by alpha count. Moreover, a direct geologic time measurement method for distal tephra was developed by pottasium-argon method. It makes possible direct measurement of geological time of young pyroclastic flow sediment. (S.Y.)

Development of cermets for high-level radioactive waste fixation

International Nuclear Information System (INIS)

Aaron, W.S.; Quinby, T.C.; Kobisk, E.H.

1979-01-01

A method is currently under development for the solidification and fixation of commercial and defense high-level radioactive wastes in the form of ceramic particles encapsulated by metal, i.e., a cermet. The chemical and physical processing techniques which have been developed and the properties of the resulting cermet bodies are described in this paper. These cermets have the advantages of high thermal conductivity and low leach rates

Geologic disposal of radioactive waste: Ethical and technical issues

International Nuclear Information System (INIS)

Pigford, T.H.

1999-01-01

defensible doses that show that future people will be protected as well as present-day people are protected from licensed nuclear facilities? If so, the need for a geologic repository could be balanced against the desire for assuring such conservative and careful protection of public health. Relaxation of the safety standard itself, as attempted so prematurely by the House and Senate bills of the present and last Congress, should be made only after special review of that need by the scientific community and the public and approval by Congress. The desire for safeguards protection of buried spent nuclear fuel will be an additional burden on repository design and prediction of performance. Thus, the Yucca Mountain Project faces a demanding technical challenge. Similar challenges face policy makers. They must reject pressures for short-term expediency and economy lest, by enacting policies that compromise scientific validity and credibility, they further undermine public confidence and irreparably harm the programs for disposing of high-level radioactive waste

Role of geochemical factors in the assessment and regulation of geologic disposal of high-level radioactive waste

International Nuclear Information System (INIS)

O'Kelley, G.D.; Meyer, R.E.

1984-03-01

It is generally agreed that in a deep repository for high-level radioactive waste, the agent most likely to mobilize radionuclides and disperse them into the accessible environment is groundwater. Analyses of the performance of a high-level waste repository will require a detailed study of the chemical factors involved in the interaction of water-mobilized nuclides with the host rock. These chemical factors include sorption phenomena, redox processes, the roles of hydrolysis and complexation in the determination of speciation, solubility, and the formation of polymeric and colloidal forms of the nuclides. A discussion and review of these factors is given along with their pertinence to the migration of the nuclides and the development of computer codes for the prediction of this migration. Of particular interest are the formation of negatively charged species of the nuclides, which tend to exhibit very low adsorption, and the formation of insoluble products through redox processes. Knowledge of the different chemical factors must be used to postulate geochemical scenarios for the release of nuclides. Much of the chemistry of the nuclides is very sensitive to pH and redox conditions and, in general, increase of acidity and oxidizing power of the groundwater could have serious consequences with respect to mobilization of the nuclides. 33 references

2008 State-of-the-Art : High Level Radioactive Waste Disposal Facilities and Project Review of Proceding Countries

Energy Technology Data Exchange (ETDEWEB)

Choi, Heui Joo; Choi, Jong Won; Lee, Jong Youl; Jung, Jong Tae; Kim, Sung Ki; Lee, Min Soo; Cho, Dong Keun; Kook, Dong Hak

2008-11-15

High level radioactive waste disposal system project for advanced nuclear fuel cycle produced this report which are dealing with the repository status of proceding countries as of 2008. This report has brief review on disposal facilities which are operating and will be operating and on future plan of those nations. The other report 'Development of the Geological Disposal System for High Level Waste' which was produced like this report time and this report would help the readers grasp the current repository status. Because our country is a latecomer in the HLW disposal world, it is strongly recommended to catch up with advanced disposal system and concepts of developed nations and this report is expected to make it possible. There are several nations which were the main survey target; Finland, USA, Sweden, Germany, France, Switzerland, and Japan. Recent information was applied to this report and our project team will produce annual state-of-the-art report with continuous updates.

Feasibility of large volume casting cementation process for intermediate level radioactive waste

International Nuclear Information System (INIS)

Chen Zhuying; Chen Baisong; Zeng Jishu; Yu Chengze

1988-01-01

The recent tendency of radioactive waste treatment and disposal both in China and abroad is reviewed. The feasibility of the large volume casting cementation process for treating and disposing the intermediate level radioactive waste from spent fuel reprocessing plant in shallow land is assessed on the basis of the analyses of the experimental results (such as formulation study, solidified radioactive waste properties measurement ect.). It can be concluded large volume casting cementation process is a promising, safe and economic process. It is feasible to dispose the intermediate level radioactive waste from reprocessing plant it the disposal site chosen has resonable geological and geographical conditions and some additional effective protection means are taken

Techno-economic Comparison of Geological Disposal of Carbon Dioxide and Radioactive Waste

International Nuclear Information System (INIS)

2014-12-01

The reduction of greenhouse gas emissions is an important prerequisite for sustainable development. The energy sector is a major contributor to such emissions, which are mostly from fossil fuel fired power plants acting as point sources of carbon dioxide (CO 2 ) discharges. For the last twenty years, the new technology of carbon capture and storage, which mitigates CO 2 emissions, has been considered in many IAEA Member States. This technology involves the removal of CO 2 from the combustion process and its disposal in geological formations, such as depleted oil or gas fields, saline aquifers or unmineable coal seams. A large scale energy supply option with low CO 2 emissions is nuclear power. The high level radioactive waste produced during nuclear power plant operation and decommissioning as well as in nuclear fuel reprocessing is also planned to be disposed of in deep geological formations. To further research and development in these areas and to compare and learn from the planning, development and implementation of these two underground waste disposal concepts, the IAEA launched the coordinated research project (CRP) Techno-economic Comparison of Ultimate Disposal Facilities for Carbon Dioxide and Radioactive Waste. The project started in 2008 and was completed in 2012. The project established an international network of nine institutions from nine IAEA Member States, representing both developing and developed countries. The CRP results compared the geological disposal facilities in the following areas: geology, environmental impacts, risk and safety assessment, monitoring, cost estimation, public perception, policy, regulation and institutions. This publication documents the outcome of the CRP and is structured into thematic chapters, covering areas analysed. Each chapter was prepared under the guidance of a lead author and involved co-authors from different Member States with diverse expertise in related areas. Participants drew on the results of earlier

Leach behavior of high-level borosilicate glasses under deep geological environment

International Nuclear Information System (INIS)

Kim, Seung Soo; Chun, Kwan Sik; Park, Hyun Soo

1998-02-01

This report presents an overview of the activities in high-level radioactive waste glass which is considered as the most practicable form of waste, and also is intended to be used in the disposal of national high-level radioactive waste in future. Leach theory of waste glass and the leach effects of ground water, metal barrier, buffer materials and rocks on the waste glass were reviewed. The leach of waste glass was affected by various factors such as composition, pH and Eh of ground water, temperature, pressure, radiation and humic acid. The crystallization, crack, weathering and the formation of altered phases of waste glass which is expected to occur in real disposal site were reviewed. The results of leaching in laboratory and in-situ were compared. The behaviors of radioactive elements leached from waste glass and the use of basalt glass for the long-term natural analogue of waste glass were also written in this report. The appraisal of durability of borosilicate waste glass as a waste media was performed from the known results of leach test and international in-situ tests were introduced. (author). 134 refs., 15 tabs., 24 figs

Argentine project for the final disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Palacios, E.; Ciallella, N.R.; Petraitis, E.J.

1989-01-01

From 1980 Argentina is carrying out a research program on the final disposal of high level radioactive wastes. The quantity of wastes produced will be significant in next century. However, it was decided to start with the studies well in advance in order to demonstrate that the high level wastes could be disposed in a safety way. The option of the direct disposal of irradiated fuel elements was discarded, not only by the energetic value of the plutonium, but also for ecological reasons. In fact, the presence of a total inventory of actinides in the non-processed fuel would imply a more important radiological impact than that caused if the plutonium is recycled to produce energy. The decision to solve the technological aspects connected with the elimination of high-level radioactive wastes well in advance, was made to avoid transfering the problem to future generations. This decision is based not only on technical evaluations but also on ethic premises. (Author)

Current status of geoscientific studies being conducted by Japan Nuclear Cycle Development Institute in regard to geological disposal of high-level radioactive waste. Pt. 2. Horonobe Underground Research Center

International Nuclear Information System (INIS)

Eki, Nobuhiro; Yamazaki, Shinichi

2004-01-01

Japan Nuclear Cycle Development Institute (JNC) has been conducting two Underground Research Laboratory (URL) Projects. 'The Long-term Program for Research, Development and Utilization of Atomic Energy (Atomic Energy Commission, 2000)' states their technical and social importance for the Japan's program for the Geological Disposal (GD) of HLW and shows an expectation of earlier execution of the projects. One of the URL projects is Neogene argillaceous sedimentary formation hosted Horonobe URL Project. The aims of the Horonobe URL project are; Presenting concrete geological environment as an example of sedimentary formation, Confirming reliability of technologies for geological disposal of High-Level Radioactive Waste (HLW) by applying them to actual geological condition of sedimentary formation, Providing opportunities to experience the actual deep underground circumstance for the general public. The project is composed of six subjects; 1) development of site characterization methodology, 2) development of monitoring techniques, 3) development of engineering techniques for underground development, 4) neotectonic characterization of the area, 5) development of engineering techniques for designing, construction and operation of a repository, 6) development of safety assessment methodology. The project consists of three phases: investigations form the surface (Phase 1), investigations during construction of the underground facility (Phase 2) and researches using the facility (Phase 3). The total duration is about 20 years. From 2000, surface-based site investigations are going on. In course of the investigations, a series of geophysical surveys has been employed. Along with the town-wide investigation, an area for site-scale investigation was selected, a land for facilities construction was acquired in the area and the land preparation has started in 2003. Geological information gave more detailed and concrete figure of URL, which is composed of three shafts down to

Treatment and Storage of High-Level Radioactive Wastes. Proceedings of the Symposium on Treatment and Storage of High-Level Radioactive Wastes

International Nuclear Information System (INIS)

1963-01-01

A variety of radioactive materials having no immediate use result from the utilization of atomic energy. The manner in which these materials are handled has repercussions on reactor economy and technology, on the health and safety of persons and populations and on atomic legislation. Excellent progress has been made in developing a technology capable of safely and economically dealing with these materials so that no immediate problems exist. The highly radioactive ''wastes'' arising from the reprocessing of irradiated fuel pose long-range problems, however, and methods for the ultimate disposal of these wastes must be developed and evaluated. Such development and evaluation can be materially assisted by providing the scientists doing the work with an opportunity of exchanging ideas and information on their experience. Therefore, the IAEA, as part of its programme of promoting nuclear technology, convened in Vienna from 8-12 October 1962 the Symposium on the Treatment and Storage of High-level Radioactive Wastes. The Symposium was attended by 130 scientists from 19 countries and two international organizations. Thirty-three papers were presented and discussed in full and formed a background for a panel discussion of chairmen near the end of the Symposium. The papers and a record of the discussions are published in this single volume. It is hoped that the information thus recorded will achieve the desired purpose of assisting the peaceful development of atomic energy

Mining and engineering aspects and variants for the underground construction of a deep geological repository for radioactive waste and spent nuclear fuel

International Nuclear Information System (INIS)

Milchev, M.; Michailov, B.; Nanovska, E.; Harizanov, A.

2003-01-01

The aim of the present report is to investigate and to describe systematically the foreign experience, scientific and technical achievements and stages of development concerning the mining and engineering aspects and variants for underground construction of a deep geological repository for radioactive waste (RAW) and spent nuclear fuel (SNF). The ideal solution in managing the problems with harmful wastes seems to be either to remove them permanently from Earth (which is related with high risks and high costs) or to transform long-lived radionuclides to short-lived radionuclides using nuclear transmutation processes in a reactor or a particle accelerator. The latter is also a complex and immensely costly process and it can only reduce the quantities of some long-lived radionuclides, which can be then disposed in a geological repository. At present, the deep geological disposal remains the only solution for solving the problem with the hazard of storing radioactive wastes. The report submits a brief description and systematization of the performed investigations, accompanied by analysis of the scientific and technical level on world scale. The analysis is related with the particular geological conditions and the existing scientific studies available so far in Bulgaria. The main conclusions are that the complex scientific-technical and engineering problems related with the construction of a deep geological repository for RAW and SNF require long-term scientific investigations and preliminary complex works and it is high time to launch them in Bulgaria. (authors)

Evaluation of S-type fiberglass composites for use in high-level radioactive waste environments

International Nuclear Information System (INIS)

Parra, S.A.

1996-01-01

Two types of S-type fiberglass materials were evaluated for use in a high-level radioactive waste environment. The S-type fiberglass composites tested were in the form of tubes and were exposed to a simulated high-level radioactive waste environment consisting of corrosive chemicals, high gamma radiation, and elevated temperatures. The physical properties of the exposed and unexposed tube samples were compared to determine the effects of the simulated environment on the S-type fiberglass composites

Efficient handling of high-level radioactive cell waste in a vitrification facility analytical laboratory

International Nuclear Information System (INIS)

Roberts, D.W.; Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, South Carolina, is the world''s largest and the United State''s first high level waste vitrification facility. For the past 1.5 years, DWPF has been vitrifying high level radioactive liquid waste left over from the Cold War. The vitrification process involves the stabilization of high level radioactive liquid waste into borosilicate glass. The glass is contained in stainless steel canisters. DWPF has filled more than 200 canisters 3.05 meters (10 feet) long and 0.61 meters (2 foot) diameter. Since operations began at DWPF in March of 1996, high level radioactive solid waste continues to be generated due to operating the facility''s analytical laboratory. The waste is referred to as cell waste and is routinely removed from the analytical laboratories. Through facility design, engineering controls, and administrative controls, DWPF has established efficient methods of handling the high level waste generated in its laboratory facility. These methods have resulted in the prevention of undue radiation exposure, wasted man-hours, expenses due to waste disposal, and the spread of contamination. This level of efficiency was not reached overnight, but it involved the collaboration of Radiological Control Operations and Laboratory personnel working together to devise methods that best benefited the facility. This paper discusses the methods that have been incorporated at DWPF for the handling of cell waste. The objective of this paper is to provide insight to good radiological and safety practices that were incorporated to handle high level radioactive waste in a laboratory setting

Risk analysis of geological disposal of radioactive waste

International Nuclear Information System (INIS)

Girardi, F.; de Marsily, G.; Weber, J.

1980-01-01

The problems of risk analysis of geological disposal of radioactive waste are briefly summarized. Several characteristics, such as the very long time span considered, make it rather unique among the problems of modern society. The safety of nuclear waste disposal in geological formations is based on several barriers, natural and man-made, which prevent disposed radionuclides from reaching the biosphere. They include a) the physico-chemical form of conditioned waste, b) the waste container, c) the geological isolation, d) buffering and backfilling materials, radionuclide retention in the geosphere and e) environmental dilution and isolation processes. The knowledge available on each barrier and its modelling is reviewed. Specific disposal strategies in clay, granite and salt formations are considered, outlining the performance of the barriers in each particular strategy, and results obtained in preliminary evaluations

The safety case for deep geological disposal of radioactive waste

International Nuclear Information System (INIS)

Kwong, Gloria

2014-01-01

The concept of a 'safety case' for a deep geological repository for radioactive waste was first introduced by the NEA Expert Group on Integrated Performance Assessment (IPAG). It was further developed in the NEA report entitled Confidence in the Long-term Safety of Deep Geological Repositories (1999), and since then it has been taken up in international safety standards as promulgated by the International Atomic Energy Agency (IAEA, 2006, 2011) and more recently in recommendations by the International Commission on Radiological Protection on the application of the system of radiological protection in geological disposal (ICRP, 2013). Many national radioactive waste disposal programmes and regulatory guides are also applying this concept. The NEA has used the safety case as a guide in several international peer reviews of national repository programmes and safety documentation. In Europe, the EU Directive 2011/70/ Euratom (EU, 2011) establishes a framework to ensure responsible and safe management of spent fuel and radioactive waste by member states that, inter alia, requires a decision-making process based on safety evidence and arguments that mirror the safety case concept. In 2007, the NEA, the IAEA and the European Commission (EC) organised a symposium on Safety Cases for the Deep Disposal of Radioactive Waste: Where Do We Stand? Since this time, however, there have been some major developments in a number of national geological disposal programmes and significant experience in preparing and reviewing cases for the operational and long-term safety of proposed and operating geological repositories. A symposium on The Safety Case for Deep Geological Disposal of Radioactive Waste: 2013 State of the Art was thus organised to assess developments since 2007 in the practice, understanding and roles of the safety case, as applied internationally at all stages of repository development, including the interplay of technical, regulatory and societal issues. The symposium

Clay 2001 dossier: progress report on feasibility studies and research into deep geological disposal of high-level, long-lived waste

International Nuclear Information System (INIS)

2001-12-01

A French Act of Parliament passed on 30 December 1991 set out the main areas of research required to prepare solutions for the long-term management of high-level, long-lived radioactive waste. The three avenues of research listed in the Act included a feasibility study of the deep geological disposal of these waste, with responsibility for steering the study given to ANDRA, France National Agency for Radioactive Waste Management. Following government decisions taken in 1998, the study focused on two types of geological medium, clay and granite. The clay formations study is essentially based on results from an underground laboratory sited at the border between the Meuse and Haute-Marne departments, where the Callovo-Oxfordian argillite beds are being investigated. No site has yet been chosen for an underground laboratory for the granite study, so for the time being this will draw on generic work and on research carried out in laboratories outside France. ANDRA has decided to present an initial report on the results of its research programme, publishing a dossier on the work on clay formations in 2001 with a second dossier covering the work on granite due for release in 2002. This dossier is thus a review of the work carried out by ANDRA on the feasibility study into a radioactive waste repository in a clay formation. It represents one step in a process of studies and research work leading up to the submission of a report due in 2005 containing ANDRA conclusions on the feasibility of a repository in the clay formation. (author)

Managing the nation's high-level radioactive waste: key issues and recommendations

International Nuclear Information System (INIS)

1981-07-01

To date, no unified national plan has been adopted to develop and implement a comprehensive system of management and disposal of high-level radioactive waste in the United States. Growing public concern about this problem has resulted in a number of recent efforts to develop a national high-level waste management policy. The 96th Congress strove to resolve the central issues, but ultimately failed to pass legislation, partly because of disagreements about the appropriate role of states in the siting of repositories for military waste. Outside government, a number of organizations convened representatives of diverse groups concerned with national high-level radioactive waste management to seek agreement on the major elements of national policy. One such organization was RESOLVE, Center for Environmental Conflict Resolution, which in May 1981 was merged into The Conservation Foundation. RESOLVE convened Forum II, a series of discussions among representatives of environmental, industrial, governmental, and citizen interest groups, in 1981 specifically to address the issues blocking Congressional agreement on high-level waste policy. This report contains the recommendations which resulted from these deliberations. Reprocessing, interim storage, respository development, and licensing requirements are addressed. Federal, state, and public participation in decision making are also discussed

High-level waste-form-product performance evaluation

International Nuclear Information System (INIS)

Bernadzikowski, T.A.; Allender, J.S.; Stone, J.A.; Gordon, D.E.; Gould, T.H. Jr.; Westberry, C.F. III.

1982-01-01

Seven candidate waste forms were evaluated for immobilization and geologic disposal of high-level radioactive wastes. The waste forms were compared on the basis of leach resistance, mechanical stability, and waste loading. All forms performed well at leaching temperatures of 40, 90, and 150 0 C. Ceramic forms ranked highest, followed by glasses, a metal matrix form, and concrete. 11 tables

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)

Report of ICRP Task Group 80: 'radiological protection in geological disposal of long-lived solid radioactive waste'.

Science.gov (United States)

Weiss, W

2012-01-01

The report of International Commission on Radiological Protection (ICRP) Task Group 80 entitled 'Radiological protection in geological disposal of long-lived solid radioactive waste' updates and consolidates previous ICRP recommendations related to solid waste disposal (ICRP Publications 46, 77, and 81). The recommendations given in this report apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the 2007 system of radiological protection, described in ICRP Publication 103, can be applied in the context of the geological disposal of long-lived solid radioactive waste. The report is written as a self-standing document. It describes the different stages in the lifetime of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences application of the protection system over the different phases in the lifetime of a disposal facility is the level of oversight that is present. The level of oversight affects the capability to reduce or avoid exposures. Three main time frames have to be considered for the purpose of radiological protection: time of direct oversight when the disposal facility is being implemented and active oversight is taking place; time of indirect oversight when the disposal facility is sealed and indirect oversight is being exercised to provide additional assurance on behalf of the population; and time of no oversight when oversight is no longer exercised because memory is lost. Copyright © 2012. Published by Elsevier Ltd.

Main outcomes from in situ thermo-hydro-mechanical experiments programme to demonstrate feasibility of radioactive high-level waste disposal in the Callovo-Oxfordian claystone

Directory of Open Access Journals (Sweden)

G. Armand

2017-06-01

Full Text Available In the context of radioactive waste disposal, an underground research laboratory (URL is a facility in which experiments are conducted to demonstrate the feasibility of constructing and operating a radioactive waste disposal facility within a geological formation. The Meuse/Haute-Marne URL is a site-specific facility planned to study the feasibility of a radioactive waste disposal in the Callovo-Oxfordian (COx claystone. The thermo-hydro-mechanical (THM behaviour of the host rock is significant for the design of the underground nuclear waste disposal facility and for its long-term safety. The French National Radioactive Waste Management Agency (Andra has begun a research programme aiming to demonstrate the relevancy of the French high-level waste (HLW concept. This paper presents the programme implemented from small-scale (small diameter boreholes to full-scale demonstration experiments to study the THM effects of the thermal transient on the COx claystone and the strategy implemented in this new programme to demonstrate and optimise current disposal facility components for HLW. It shows that the French high-level waste concept is feasible and working in the COx claystone. It also exhibits that, as for other plastic clay or claystone, heating-induced pore pressure increases and that the THM behaviour is anisotropic.

High level nuclear wastes

International Nuclear Information System (INIS)

Lopez Perez, B.

1987-01-01

The transformations involved in the nuclear fuels during the burn-up at the power nuclear reactors for burn-up levels of 33.000 MWd/th are considered. Graphs and data on the radioactivity variation with the cooling time and heat power of the irradiated fuel are presented. Likewise, the cycle of the fuel in light water reactors is presented and the alternatives for the nuclear waste management are discussed. A brief description of the management of the spent fuel as a high level nuclear waste is shown, explaining the reprocessing and giving data about the fission products and their radioactivities, which must be considered on the vitrification processes. On the final storage of the nuclear waste into depth geological burials, both alternatives are coincident. The countries supporting the reprocessing are indicated and the Spanish programm defined in the Plan Energetico Nacional (PEN) is shortly reviewed. (author) 8 figs., 4 tabs

Expertise on the provision of evidence with respect to Nagra's disposal concept for spent fuel assemblies, vitrified high-level radioactive waste as well as for long-living intermediate-level wastes (Opalinus clay project)

International Nuclear Information System (INIS)

2005-08-01

Mankind has been living in a field of natural radiation; in Switzerland, the natural dose is around 3 mSv per year. It can be assumed that an artificial dose smaller than the natural one is harmless and can therefore be tolerated. However, nuclear power plants, medicine, industry and research produce radioactive wastes whose radioactivity is mostly higher than the natural level. These wastes must therefore be concentrated and enclosed until the decay reduces the dose rate to a harmless level. For this, it is foreseen that the radioactive wastes will be disposed of in deep-lying geological strata. The enclosure must be guarantied in such a way that, at any time, the radiation suffered by mankind and environment due to the radioactive wastes stays under the statutory limit of 1 mSv/a. The judgement of the quality of the deep underground repository is divided into 3 chapters: a) based on the geological and hydro-geological properties of the host rock, the proof of safety shows that the chosen repository site is safe for the long term; b) the proof of site guaranties that the repository needed can be built in the chosen host rock; c) the proof of implementation demonstrates that the repository can be built with the actual technical means proposed. The forecast for the development of the safety of the repository in the long term is fairly inaccurate, the most difficult factor being the developments in mankind's way of life. Therefore, conservative assumptions must be taken into account to cover even the most unlikely cases. The former project 'Gewaehr' presented by the National Co-operative for the Disposal of Nuclear Wastes (NAGRA) in 1978 was based on crystalline rock; it was rejected because it was not possible to find a sufficiently large area without geologic faults for the repository. In new investigations, NAGRA found a suitable layer of Opalinus clay in Zurich's Weinland. In the neighbourhood of the layer discovered, there are neither noticeable beds of other

Deep storage of radioactive waste from a geological point of view

International Nuclear Information System (INIS)

Venzlaff, Helmut

2015-01-01

For a deep storage of radioactive waste geologists gave their preference to salt prior to other rock complexes such as clay or granite. Major deposits from pure rock salt are particularly suitable to safely seal radioactive wastes from the biosphere because due to their plasticity they are free from fissures in which liquids and gases could circulate and because their thermal conductivity is higher than of other rocks. The geological stability of salt domes can be shown by their geological evolution. Thus the salt dome in Gorleben was formed 100 million years ago and is older than the Atlantic, the Alps or the ascent of the low mountain range. During this long period it survived ocean floods, mountain formations, earthquakes, volcanism and ice ages without considerably changing its shape. There are no geological reasons, why it should not remain stable during the next million years.

Deep storage of radioactive waste from a geological point of view

Energy Technology Data Exchange (ETDEWEB)

Venzlaff, Helmut [Federal Institute for Geo-Sciences and Raw Materials, Hannover (Germany)

2015-08-15

For a deep storage of radioactive waste geologists gave their preference to salt prior to other rock complexes such as clay or granite. Major deposits from pure rock salt are particularly suitable to safely seal radioactive wastes from the biosphere because due to their plasticity they are free from fissures in which liquids and gases could circulate and because their thermal conductivity is higher than of other rocks. The geological stability of salt domes can be shown by their geological evolution. Thus the salt dome in Gorleben was formed 100 million years ago and is older than the Atlantic, the Alps or the ascent of the low mountain range. During this long period it survived ocean floods, mountain formations, earthquakes, volcanism and ice ages without considerably changing its shape. There are no geological reasons, why it should not remain stable during the next million years.

Pre-construction geologic section along the cross drift through the potential high-level radioactive waste repository, Yucca Mountain, Nye County, Nevada

International Nuclear Information System (INIS)

Potter, C.J.; Day, W.C.; Sweetkind, D.S.; Juan, C.S.; Drake, R.M. II

1998-01-01

As part of the Site Characterization effort for the US Department of Energy's Yucca Mountain Project, tunnels excavated by tunnel boring machines provide access to the volume of rock that is under consideration for possible underground storage of high-level nuclear waste beneath Yucca Mountain, Nevada. The Exploratory Studies Facility, a 7.8-km-long, 7.6-m-diameter tunnel, has been excavated, and a 2.8-km-long, 5-m-diameter Cross Drift will be excavated in 1998 as part of the geologic, hydrologic and geotechnical evaluation of the potential repository. The southwest-trending Cross Drift branches off of the north ramp of the horseshoe-shaped Exploratory Studies Facility. This report summarizes an interpretive geologic section that was prepared for the Yucca Mountain Project as a tool for use in the design and construction of the Cross Drift

Evolution in radioactive waste countermeasures

International Nuclear Information System (INIS)

Moriguchi, Yasutaka

1984-01-01

The establishment of radioactive waste management measures is important to proceed further with nuclear power development. While the storage facility projects by utilities are in progress, large quantity of low level wastes are expected to arise in the future due to the decommissioning of nuclear reactors, etc. An interim report made by the committee on radioactive waste countermeasures to the Atomic Energy Commission is described as follows: the land disposal measures of ultra-low level and low level radioactive wastes, that is, the concept of level partitioning, waste management, the possible practice of handling wastes, etc.; the treatment and disposal measures of high level radioactive wastes and transuranium wastes, including task sharing among respective research institutions, the solidification/storage and the geological formation disposal of high level wastes, etc. (Mori, K.)

Radioactive waste management

International Nuclear Information System (INIS)

Blomek, D.

1980-01-01

The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

Hydrogeologic factors in the selection of shallow land burial sites for the disposal of low-level radioactive waste

Science.gov (United States)

Fischer, John N.

1986-01-01

In the United States, low-level radioactive waste is disposed of by shallow land burial. Commercial low-level radioactive waste has been buried at six sites, and low-level radioactive waste generated by the Federal Government has been buried at nine major and several minor sites. Several existing low-level radioactive waste sites have not provided expected protection of the environment. These shortcomings are related, at least in part, to an inadequate understanding of site hydrogeology at the time the sites were selected. To better understand the natural systems and the effect of hydrogeologic factors on long-term site performance, the U.S. Geological Survey has conducted investigations at five of the six commercial low-level radioactive waste sites and at three Federal sites. These studies, combined with those of other Federal and State agencies, have identified and confirmed important hydrogeologic factors in the effective disposal of low-level radioactive waste by shallow land burial. These factors include precipitation, surface drainage, topography, site stability, geology, thickness of the host soil-rock horizon, soil and sediment permeability, soil and water chemistry, and depth to the water table.

Application of Ga-Al discrimination plots in identification of high strength granitic host rocks for deep geological repository of high level radioactive waste

International Nuclear Information System (INIS)

Bajpai, R.K.; Narayan, P.K.; Trivedi, R.K.; Purohit, M.K.

2010-01-01

The permanent disposal of vitrified high level wastes and in some cases even spent fuel, is being planned in specifically designed and built deep geological repository located in the depth range of 500-600m in appropriate host rock at carefully selected sites. Such facilities are expected to provide very long term isolation and confinement to the disposed waste by means of long term mechanical stability of such structures that results from very high strength and homogeneity of the chosen rock, geochemical compatible environment around the disposed waste and general lack of groundwater. In Indian geological repository development programme, granites have been selected as target host rock and large scale characterization studies have been undertaken to develop database of mineralogy, petrology, geochemistry and rock mechanical characteristics. The paper proposes a new approach for demarcation of high strength homogeneous granite rocks from within an area of about 100 square kilometres wherein a cocktail of granites of different origins with varying rock mass characteristics co exists. The study area is characterised by the presence of A, S and I type granites toughly intermixed. The S type granites are derived from sedimentary parent material and therefore carry relics of parent fabric and at times undigested material with resultant reduction in their strength and increased inhomogeneity. On the other hand I type varieties are derived from igneous parents and are more homogeneous with sufficient strength. The A type granites are emplaced as molten mass in a complete non-tectonic setting with resultant homogeneous compositions, absence of tectonic fabric and very high strength. Besides they are silica rich with less vulnerability to alterations with time. Thus A type granites are most suited for construction of Deep Geological Repository. For developing a geochemical approach for establishing relation between chemical compositions and rock strength parameters, a

Solidification of high-level radioactive wastes. Final report

International Nuclear Information System (INIS)

1979-06-01

A panel on waste solidification was formed at the request of the Nuclear Regulatory Commission to study the scientific and technological problems associated with the conversion of liquid and semiliquid high-level radioactive wastes into a stable form suitable for transportation and disposition. Conclusions reached and recommendations made are as follows. Many solid forms described in this report could meet standards as stringent as those currently applied to the handling, storage, and transportation of spent fuel assemblies. Solid waste forms should be selected only in the context of the total radioactive waste management system. Many solid forms are likely to be satisfactory for use in an appropriately designed system, The current United States policy of deferring the reprocessing of commercial reactor fuel provides additional time for R and D solidification technology for this class of wastes. Defense wastes which are relatively low in radioactivity and thermal power density can best be solidified by low-temperature processes. For solidification of fresh commercial wastes that are high in specific activity and thermal power density, the Panel recommends that, in addition to glass, the use of fully-crystalline ceramics and metal-matrix forms be actively considered. Preliminary analysis of the characteristics of spent fuel pins indicates that they may be eligible for consideration as a waste form. Because the differences in potential health hazards to the public resulting from the use of various solid form and disposal options are likely to be small, the Panel concludes that cost, reliability, and health hazards to operating personnel will be major considerations in choosing among the options that can meet safety requiremens. The Panel recommends that responsibility for all radioactive waste management operations (including solidification R and D) should be centralized

Branch technical position on the use of expert elicitation in the high-level radioactive waste program

International Nuclear Information System (INIS)

Kotra, J.P.; Lee, M.P.; Eisenberg, N.A.; DeWispelare, A.R.

1996-11-01

Should the site be found suitable, DOE will apply to the US Nuclear Regulatory Commission for permission to construct and then operate a proposed geologic repository for the disposal of spent nuclear fuel and other high-level radioactive waste at Yucca Mountain. In deciding whether to grant or deny DOE's license application for a geologic repository, NRC will closely examine the facts and expert judgment set forth in any potential DOE license application. NRC expects that subjective judgments of individual experts and, in some cases, groups of experts, will be used by DOE to interpret data obtained during site characterization and to address the many technical issues and inherent uncertainties associated with predicting the performance of a repository system for thousands of years. NRC has traditionally accepted, for review, expert judgment to evaluate and interpret the factual bases of license applications and is expected to give appropriate consideration to the judgments of DOE's experts regarding the geologic repository. Such consideration, however, envisions DOE using expert judgments to complement and supplement other sources of scientific and technical information, such as data collection, analyses, and experimentation. In this document, the NRC staff has set forth technical positions that: (1) provide general guidelines on those circumstances that may warrant the use of a formal process for obtaining the judgments of more than one expert (i.e., expert elicitation); and (2) describe acceptable procedures for conducting expert elicitation when formally elicited judgments are used to support a demonstration of compliance with NRC's geologic disposal regulation, currently set forth in 10 CFR Part 60. 76 refs

Preliminary analyses of the deep geoenvironmental characteristics for the deep borehole disposal of high-level radioactive waste in Korea

Energy Technology Data Exchange (ETDEWEB)

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

2016-06-15

Spent fuels from nuclear power plants, as well as high-level radioactive waste from the recycling of spent fuels, should be safely isolated from human environment for an extremely long time. Recently, meaningful studies on the development of deep borehole radioactive waste disposal system in 3-5 km depth have been carried out in USA and some countries in Europe, due to great advance in deep borehole drilling technology. In this paper, domestic deep geoenvironmental characteristics are preliminarily investigated to analyze the applicability of deep borehole disposal technology in Korea. To do this, state-of-the art technologies in USA and some countries in Europe are reviewed, and geological and geothermal data from the deep boreholes for geothermal usage are analyzed. Based on the results on the crystalline rock depth, the geothermal gradient and the spent fuel types generated in Korea, a preliminary deep borehole concept including disposal canister and sealing system, is suggested.

Preliminary analyses of the deep geoenvironmental characteristics for the deep borehole disposal of high-level radioactive waste in Korea

International Nuclear Information System (INIS)

Lee, Jong Youl; Lee, Min Soo; Choi, Heui Joo; Kim, Geon Young; Kim, Kyung Su

2016-01-01

Spent fuels from nuclear power plants, as well as high-level radioactive waste from the recycling of spent fuels, should be safely isolated from human environment for an extremely long time. Recently, meaningful studies on the development of deep borehole radioactive waste disposal system in 3-5 km depth have been carried out in USA and some countries in Europe, due to great advance in deep borehole drilling technology. In this paper, domestic deep geoenvironmental characteristics are preliminarily investigated to analyze the applicability of deep borehole disposal technology in Korea. To do this, state-of-the art technologies in USA and some countries in Europe are reviewed, and geological and geothermal data from the deep boreholes for geothermal usage are analyzed. Based on the results on the crystalline rock depth, the geothermal gradient and the spent fuel types generated in Korea, a preliminary deep borehole concept including disposal canister and sealing system, is suggested

Site suitability criteria for solidified high level waste repositories

International Nuclear Information System (INIS)

Heckman, R.A.; Holdsworth, T.; Towse, D.F.

1979-01-01

Activities devoted to development of regulations, criteria, and standards for storage of solidified high-level radioactive wastes are reported. The work is summarized in sections on site suitability regulations, risk calculations, geological models, aquifer models, human usage model, climatology model, and repository characteristics. Proposed additional analytical work is also summarized

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Selection of thermodynamic data of cobalt and nickel

International Nuclear Information System (INIS)

Kitamura, Akira; Yui, Mikazu; Kirishima, Akira; Saito, Takumi; Shibutani, Sanae; Tochiyama, Osamu

2009-11-01

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of cobalt and nickel have been carried out. For cobalt, extensive literature survey has been performed and all the obtained literatures have been carefully reviewed to select the thermodynamic data. Selection of thermodynamic data of nickel has been based on a thermodynamic database published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA), which has been carefully reviewed by the authors, and then thermodynamic data have been selected after surveying latest literatures. Based on the similarity of chemical properties between cobalt and nickel, complementary thermodynamic data of nickel and cobalt species expected under the geological disposal condition have been selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

Research in the selection of very low level radioactive waste disposal site in southwest China

International Nuclear Information System (INIS)

Tuo, Xianguo; Long, Qiong; Zhong, Hongmei; Xu, Zhengqi; Mu, Keliang; Gao, Lan

2008-01-01

The ultimate goal of Chinese Radioactive Nuclear Waste Management and Disposal Security is that must use proper and optimized ways to manage radioactive waste and make sure human beings and the environment either at the present or in the future can be free from any unacceptable risks. According to the goal, this paper presents an overview of comprehensive site characterization work that comprises investigations of physical geography, climatology, geology and hydrogeology, as well as geological hazard on two candidate Very Low Level Radioactive Waste (VLLW) disposal sites (Site 1 and Site 2) which are both located in the south west of China. The results showed that there are many similarities in the regional extent of the two sites, but many distinct differences are found in terrain and topographic features, granule stratum, hydraulic gradient, and so on. On the whole, the two alternative sites are in line with the requirements for very low level radioactive waste disposal, and Site 1 is superior to Site 2. (author)

Mined Geologic Disposal System Requirements Document

International Nuclear Information System (INIS)

1993-01-01

This Mined Geologic Disposal System Requirements document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) and commercial and defense high level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The development and control of the MGDS-RD is quality-affecting work and is subject to the Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Quality Assurance Requirements Document (QARD). As part of the technical requirements baseline, it is also subject to Baseline Management Plan controls. The MGDS-RD and the other program-level requirements documents have been prepared and managed in accordance with the Technical Document Preparation Plan (TDPP) for the Preparation of System Requirements Documents

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

Energy Technology Data Exchange (ETDEWEB)

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

1999-01-01

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

A Methodology to analyze the biosphere in the assessment of deep geological repositories for high level radioactive waste

International Nuclear Information System (INIS)

Pinedo, P.; Smith, G.

1996-11-01

This report summarizes the work done and the achievements reached within the R and D Project that IMA/CIEMAT has had with ENRESA during 1993-1995. The overall R and D Project has a wide radiological protection context, but the work reported here relates only to the development of a Methodology for considering the Biosphere sub-system in the assessments of deep geological repositories for high radioactive wastes (HLW). The main areas concerned within the Methodology have to do with the Biosphere structure and morphology in the long-term relevant to deep disposal of HLW: in the contexts of the assessment of these systems, and appropriate modelling of the behaviour of radionuclides released to the biosphere system and with the associated human exposure. This document first provides a review of the past and present international and national concerns about the biosphere modelling and its importance in relation to the definition of safety criteria. A joint ENRESA/ANDRA/IPSN/CIEMAT study about the definition and practical descriptions of the biosphere systems under different climatic states is then summarized. The Methodology developed by IMA/CIEMAT is outlined with an illustration of the way it works. Different steps and procedures are included for a better practical understanding of the software tools developed within the project to support the application of the Methodology. This methodology is widely based on an international working group on ''Reference Biospheres'', part of the BIOMOVS II Project. Specific software developments have been carried out in collaboration with Qunti Sci Itd and with the Polytechnical University of Madrid. (Author)

Comments of the Wisconsin Radioactive Waste Review Board's Technical Advisory Council on the review draft of the north central regional geologic and environmental characterization reports, May 1983

International Nuclear Information System (INIS)

1984-01-01

This document contains a collection of official comments on a draft report characterizing the subsurface geology of an area of Wisconsin proposed for a high-level radioactive waste disposal site. Most comments identify passages requiring correction or question the interpretation of the data

Deep geological radioactive waste disposal in Germany: Lessons learned and future perspectives

International Nuclear Information System (INIS)

Lempert, J.P.; Biurrun, E.

2001-01-01

As far back as in the seventies a fully developed, integrated concept for closing the nuclear fuel cycle was agreed upon in Germany between the Federal Government of that time and the electricity utilities. In the twenty years elapsed since then it was further developed as necessary to permanently fit the state of the art of science and technology. For management of spent fuel, the concept currently considers two equivalent alternatives: direct disposal of the spent fuel or reprocessing the fuel and recycling in thermal reactors. Interim storage of spent fuel and vitrified high level waste (HLW) to allow for decay heat generation to decrease to a convenient level is carried out in centralized installations. Radioactive waste disposal in pursuant to German regulations for all kinds of waste is to be carried out exclusively in deep geologic repositories. At present in the country, there are three centralized interim storage facilities for spent fuel, one of them can also accept vitrified HLW. Several facilities are in use for low level waste (LLW) and intermediate level waste (ILW) storage at power plants and other locations. A pilot conditioning facility for encapsulating spent fuel and/or HLW for final disposal is now ready to be commissioned. Substantial progress has been achieved in realization of HLW disposal, including demonstration of all the needed technology and fabrication of a significant part of the equipment. With regard to deep geologic disposal of LLW and ILW, Germany has worldwide unique experience. The Asse salt mine was used as an experimental repository for some 10 years in the late sixties and seventies. After serving since then as an underground research facility, it is now being backfilled and sealed. The Morsleben deep geologic repository was in operation for more than 25 years until September 1998. (author)

Geological aspects of the high level waste and spent fuel disposal programme in Slovakia

Energy Technology Data Exchange (ETDEWEB)

Matej, Gedeon; Milos, Kovacik; Jozef, Hok [Geological Survey of Slovak Republic, Bratislava (Slovakia)

2001-07-01

An autonomous programme for development of a deep geological high level waste and spent fuel disposal began in 1996. One of the most important parts in the programme is siting of the future deep seated disposal. Geological conditions in Slovakia are complex due to the Alpine type tectonics that formed the geological environment during Tertiary. Prospective areas include both crystalline complexes (tonalites, granites, granodiorites) and Neogene (Miocene) argillaceous complexes. (author)

A Study on Site Selecting for National Project including High Level Radioactive Waste Disposal

Energy Technology Data Exchange (ETDEWEB)

Kim, Kilyoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Many national projects are stopped since sites for the projects are not determined. The sites selections are hold by NIMBY for unpleasant facilities or by PYMFY for preferable facilities among local governments. The followings are the typical ones; NIMBY projects: high level radioactive waste disposal, THAAD, Nuclear power plant(NPP), etc. PIMFY projects: South-east new airport, KTX station, Research center for NPP decommission, etc. The site selection for high level radioactive waste disposal is more difficult problem, and thus government did not decide and postpone to a dead end street. Since it seems that there is no solution for site selection for high level radioactive waste disposal due to NIMBY among local governments, a solution method is proposed in this paper. To decide a high level radioactive waste disposal, the first step is to invite a bid by suggesting a package deal including PIMFY projects such as Research Center for NPP decommission. Maybe potential host local governments are asked to submit sealed bids indicating the minimum compensation sum that they would accept the high level radioactive waste disposal site. If there are more than one local government put in a bid, then decide an adequate site by considering both the accumulated PESS point and technical evaluation results. By considering how fairly preferable national projects and unpleasant national projects are distributed among local government, sites selection for NIMBY or PIMFY facilities is suggested. For NIMBY national projects, risk, cost benefit analysis is useful and required since it generates cost value to be used in the PESS. For many cases, the suggested method may be not adequate. However, similar one should be prepared, and be basis to decide sites for NIMBY or PIMFY national projects.

Geology, Bedrock, Tabular data involving the location of design specifics for wells related to the Low-level Radioactive Waste (LLRW) Site Characterization., Published in 1998, North Carolina Department of Environment and Natural Resources (DENR).

Data.gov (United States)

NSGIC State | GIS Inventory — Geology, Bedrock dataset current as of 1998. Tabular data involving the location of design specifics for wells related to the Low-level Radioactive Waste (LLRW) Site...

China's status and strategy of radioactive waste management

International Nuclear Information System (INIS)

Bi Decai

2001-01-01

China has a forty-year history of nuclear industry and nuclear technology application. Safety management of radioactive wastes has been the great concern of related regulatory authorities. After the national policy on regional disposal for low and intermediate level radioactive waste was enacted in 1992, the management of radioactive wastes gradually focused on disposal. Currently, the strategies for radioactive waste management in China are: (a) storing high level radioactive wastes temporarily and launching the study of vitrification and deep geological disposal of high level liquid waste, treating spent fuels from PWR by reprocessing; (b) implementing regional disposal policy for low and intermediate level wastes, implementing cement solidification for low and intermediate level liquid waste before disposal, carrying out bulk casting shallow land disposal technology and hydraulic-fractured cement solidification for deep geological disposal in some special regions under specific conditions, treating low and intermediate level solid radioactive wastes by cement solidification after incineration or by compressing before final disposal; (c) stabilizing the tailing repository by reinforcing embankment, constructing flood dam and overlaying plantation; and (d) developing and formulating laws, regulations, and standards to ensure safe management of radioactive wastes. When establishing standards, other than to follow the generic principles and requirements, emphasis should be placed on the following principles: safety the first, economy, disposal of radioactive wastes as focus, and introduction of international advanced standards as possible. (author)

Feasibility of disposal of high-level radioactive waste into the seabed. Volume 8: Review of processes near a buried waste canister

International Nuclear Information System (INIS)

Lanza, F.

1988-01-01

One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and infomation exchange among the Member countries participating in the NEA Seabed Working Group. This report investigates the phenomena arriving in the proximity of the waste package immersed in the sea sediments

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

International Nuclear Information System (INIS)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K.

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology

Low-level Radioactive waste Management

International Nuclear Information System (INIS)

1991-01-01

This meeting describes low-level radioactive waste management problems and contains 8 papers: 1 Low-level radioactive waste management: exemption concept and criteria used by international organizations. 2 Low-level radioactive waste management: french and foreign regulations 3 Low-level radioactive waste management in EDF nuclear power plants (FRANCE) 4 Low-level radioactive waste management in COGEMA (FRANCE) 5 Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE) 6 Low-level radioactive waste management in hospitals 7 Low-level radioactive waste disposal: radiation protection laws 8 Methods of low-level radioactive materials measurements during reactor dismantling or nuclear facilities demolition (FRANCE)

Synthetic hydrogeological study on Beishan preselected area for high-level radioactive waste repository in China

International Nuclear Information System (INIS)

Guo Yonghai; Su Rui; Ji Ruili; Wang Hailong; Liu Shufen; Zong Zihua; Dong Jiannan; Zhang Ming

2014-01-01

On the basis of large scale field hydrogeological investigation, synthetic hydrogeological studies related to groundwater system characteristics, permeability of rock bodies, groundwater dynamic, hydrogeochemistry, isotopic hydrology, CFC's of groundwater and groundwater flow field simulation were carried out for Beishan area, Gansu province. According to analysis on a large amount of hydrogeological data, the characteristics of groundwater circulation, groundwater hydrodynamics and hydrgeochemistry were described and the suitability of Beishan area as the potential area of high-level radioactive waste disposal was evaluated in the paper. Through this study, the hydrogeological study and evaluation methods in the siting of China's high level radioactive waste repository were set up. Furthermore, the important hydrogeological scientific evidence was provided for optimal site filtration of China's high-level radioactive waste repository in Beishan area. (authors)

Perspective of the waste management research program at NRC on modeling phenomena related to the disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Randall, J.D.; Costanzi, F.A.

1985-01-01

Modeling the geologic disposal of high-level radioactive waste falls short of ideal for a variety of reasons. The understanding of the physical processes involved may be incomplete or incorrect. It may not be possible to specify mathematically all relationships among the processes involved. The initial conditions or boundary conditions may not be known or directly measurable. Further, often it is impossible to obtain exact solutions to the mathematical relationships that constitute the mathematical model. Finally, many simplifications, approximations, and assumptions will be needed to make the models both understandable and calculationally tractable. Yet, modeling is the only means available by which any quantitative estimation of the expected performance of a geologic repository over the long term can be made. If modeling estimates of the performance of a geologic repository are to provide effective support for an NRC finding of reasonable assurance of no unreasonable risk to the public health and safety, then the strengths and limitations of the modeling process, the models themselves, and the use of the models must be understood and explored fully

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.)

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Spent fuel, high-level radioactive waste, or reactor... RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.108 Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation. The...

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

PRINCIPLE ROCK TYPES FOR RADIOACTIVE WASTE REPOSITORIES

Directory of Open Access Journals (Sweden)

Sibila Borojević Šostarić

2012-07-01

Full Text Available Underground geological storage of high- and intermediate/low radioactive waste is aimed to represent a barrier between the surface environment and potentially hazardous radioactive elements. Permeability, behavior against external stresses, chemical reacatibility and absorption are the key geological parameters for the geological storage of radioactive waste. Three principal rock types were discussed and applied to the Dinarides: (1 evaporites in general, (2 shale, and (3 crystalline basement rocks. (1 Within the Dinarides, evaporite formations are located within the central part of a Carbonate platform and are inappropriate for storage. Offshore evaporites are located within diapiric structures of the central and southern part of the Adriatic Sea and are covered by thick Mesozoic to Cenozoic clastic sediment. Under very specific circumstances they can be considered as potential site locations for further investigation for the storage of low/intermediate level radioactive wast e. (2 Thick flysch type formation of shale to phyllite rocks are exposed at the basement units of the Petrova and Trgovska gora regions whereas (3 crystalline magmatic to metamorphic basement is exposed at the Moslavačka Gora and Slavonian Mts. regions. For high-level radioactive waste, basement phyllites and granites may represent the only realistic potential option in the NW Dinarides.

Risk communication system for high level radioactive waste disposal

International Nuclear Information System (INIS)

Kugo, Akihide; Uda, Akinobu; Shimoda, Hirosi; Yoshikawa, Hidekazu; Ito, Kyoko; Wakabayashi, Yasunaga

2005-01-01

In order to gain a better understanding and acceptance of the task of implementing high level radioactive waste disposal, a study on new communication system about social risk information has been initiated by noticing the rapid expansion of Internet in the society. First, text mining method was introduced to identify the core public interest, examining public comments on the technical report of high level radioactive waste disposal. Then we designed the dialog-mode contents based on the theory of norm activation by Schwartz. Finally, the discussion board was mounted on the web site. By constructing such web communication system which includes knowledge base contents, introspective contents, and interactive discussion board, we conducted the experiment for verifying the principles such as that the basic technical knowledge and trust, and social ethics are indispensable in this process to close the perception gap between nuclear specialists and the general public. The participants of the experiment increased their interest in the topics with which they were not familiar and actively posted their opinions on the BBS. The dialog-mode contents were significantly more effective than the knowledge-based contents in promoting introspection that brought people into a greater awareness of problems such as social dilemma. (author)

Deep geological disposal of radioactive waste in Switzerland - Overview and outlook

Energy Technology Data Exchange (ETDEWEB)

Schnellmann, M.; Zuidema, P.; Gautschi, A.

2015-07-01

This article reviews the situation in Switzerland regarding the disposal of radioactive wastes. The development of the Swiss concept for wastes with high, medium and low levels of activity is reviewed, as detailed in the Sectorial Plan for Deep Geological Repositories published in 2008. The three stages involved are described in detail. Further investigations carried out in the Grimsel and Mont Terri underground laboratories are reported on. The state of current work is reviewed. A map is provided of the areas in northern Switzerland which have been selected for further, more intensive research, along with a review of the possible rock formations to be investigated. Data already obtained are reviewed and proposals for further investigations are discussed. In the upcoming stage 3 of the plan, the selection of one site per repository type will be made, leading to the submission of a general licence application.

Safety assessments for deep geological disposal of radioactive wastes

International Nuclear Information System (INIS)

Lyon, R.B.

1984-01-01

The objective of safety assessment for deep geological disposal of radioactive wastes is to evaluate how well the engineered barriers and geological setting inhibit radionuclide migration and prevent radiation dose to man. Safety assessment is influenced through interaction with the regulatory agencies, research groups, the public and the various levels of government. Under the auspices of the IAEA, a generic disposal system description has been developed to facilitate international exchange and comparison of data and results, and to enable development and comparison of performance for all components of the disposal system. It is generally accepted that a systems modelling approach is required and that safety assessment can be considered on two levels. At the systems level, all components of the system are taken into account to evaluate the risk to man. At the systems level, critical review and quality assurance on software provide the major validation techniques. Risk is a combination of dose estimate and probability of that dose. For analysis of the total system to be practical, the components are usually represented by simplified models. Recently, assessments have been taking uncertainties in the input data into account. At the detailed level, large-scale, complex computer programs model components of the system in sufficient detail that validation by comparison with field and laboratory measurements is possible. For example, three-dimensional fluid-flow, heat-transport and solute-transport computer programs have been used. Approaches to safety assessment are described, with illustrations from safety assessments performed in a number of countries. (author)

Impact of transporting defense high-level waste to a geologic repository

International Nuclear Information System (INIS)

Joy, D.S.; Shappert, L.B.; Boyle, J.W.

1984-12-01

The Nuclear Waste Policy Act of 1982 (Public Law 97-425) provides for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel and requires the Secretary of Energy to evaluate five potential repository sites. One factor that is to be examined is transportation of radioactive materials to such a repository and whether transportation might be affected by shipments to a defense-only repository, or to one that accepts both defense and commercial waste. In response to this requirement, The Department of Energy has undertaken an evaluation of the cost and risk associated with the potential shipments. Two waste-flow scenarios are considered which are related to the total quantity of defense high-level waste which will be placed in a repository. The low-flow case is based on a total of 6700 canisters being transported from one site, while the high-flow case assumes that a total of 20,000 canisters will be transported from three sites. For the scenarios considered, the estimated shipping costs range from $105 million to $257 million depending upon the mode of transport and the repository location. The total risks associated with shipping defense high-level waste to a repository are estimated to be significantly smaller than predicted for other transportation activities. In addition, the cost of shipping defense high-level waste to a repository does not depend on whether the site is a defense-only or a commercial repository. Therefore, the transportation considerations are not a basis for the selection of one of the two disposal options

Social and institutional evaluation report for Greater-Than-Class C Low-Level Radioactive Waste Disposal

International Nuclear Information System (INIS)

Anderson, T.L.; Lewis, B.E.; Turner, K.H.; Rozelle, M.A.

1993-10-01

This report identifies and characterizes social and institutional issues that would be relevant to the siting, licensing, construction, closure, and postclosure of a Greater-Than-Class-C low-level radioactive waste (GTCC LLW) disposal facility. A historical perspective of high-level radioactive waste (HLW) and LLW disposal programs is provided as an overview of radioactive waste disposal and to support the recommendations and conclusions in the report. A characterization of each issue is provided to establish the basis for further evaluations. Where applicable, the regulatory requirements of 10 CFR 60 and 61 are incorporated in the issue characterizations. The issues are used to compare surface, intermediate depth, and deep geologic disposal alternatives. The evaluation establishes that social and institutional issues do not significantly discriminate among the disposal alternatives. Recommendations are provided for methods by which the issues could be considered throughout the lifecycle of a GTCC LLW disposal program

Social and institutional evaluation report for Greater-Than-Class C Low-Level Radioactive Waste Disposal

Energy Technology Data Exchange (ETDEWEB)

Anderson, T.L.; Lewis, B.E.; Turner, K.H.; Rozelle, M.A. [Dames and Moore, Denver, CO (United States)

1993-10-01

This report identifies and characterizes social and institutional issues that would be relevant to the siting, licensing, construction, closure, and postclosure of a Greater-Than-Class-C low-level radioactive waste (GTCC LLW) disposal facility. A historical perspective of high-level radioactive waste (HLW) and LLW disposal programs is provided as an overview of radioactive waste disposal and to support the recommendations and conclusions in the report. A characterization of each issue is provided to establish the basis for further evaluations. Where applicable, the regulatory requirements of 10 CFR 60 and 61 are incorporated in the issue characterizations. The issues are used to compare surface, intermediate depth, and deep geologic disposal alternatives. The evaluation establishes that social and institutional issues do not significantly discriminate among the disposal alternatives. Recommendations are provided for methods by which the issues could be considered throughout the lifecycle of a GTCC LLW disposal program.

Natural analogues: studies of geological processes relevant to radioactive waste disposal in deep geological repositories

Energy Technology Data Exchange (ETDEWEB)

Russel, A.W. [Bedrock Geosciences, Auenstein (Switzerland); Reijonen, H.M. [Saanio and Rickkola Oy, Helsinki (Finland); McKinley, I.G. [MCM Consulting, Baden-Daettwil (Switzerland)

2015-06-15

The geological disposal of radioactive wastes is generally accepted to be the most practicable approach to handling the waste inventory built up from over 70 years accumulation of power production, research-medical-industrial and military wastes. Here, a brief overview of the approach to geological disposal is presented along with some information on repository design and the assessment of repository post-closure safety. One of the significant challenges for repository safety assessment is how to extrapolate the likely long-term (i.e. ten thousand to a million years) behaviour of the repository from the necessarily short term data from analytical laboratories and underground rock laboratories currently available. One approach, common to all fields of the geosciences, but also in such diverse fields as philosophy, biology, linguistics, law, etc., is to utilise the analogue argumentation methodology. For the specific case of radioactive waste management, the term 'natural analogue' has taken on a particular meaning associated with providing supporting arguments for a repository safety assessment. This approach is discussed here with a brief overview of how the study of natural (and, in particular, geological) systems can provide supporting information on the likely long-term evolution of a deep geological waste repository. The overall approach is discussed and some relevant examples are presented, including the use of uranium ore bodies to assess waste form stability, the investigation of native metals to define the longevity of waste containers and how natural clays can provide information on the stability of waste tunnel backfill material. (authors)

Natural analogues: studies of geological processes relevant to radioactive waste disposal in deep geological repositories

International Nuclear Information System (INIS)

Russel, A.W.; Reijonen, H.M.; McKinley, I.G.

2015-01-01

The geological disposal of radioactive wastes is generally accepted to be the most practicable approach to handling the waste inventory built up from over 70 years accumulation of power production, research-medical-industrial and military wastes. Here, a brief overview of the approach to geological disposal is presented along with some information on repository design and the assessment of repository post-closure safety. One of the significant challenges for repository safety assessment is how to extrapolate the likely long-term (i.e. ten thousand to a million years) behaviour of the repository from the necessarily short term data from analytical laboratories and underground rock laboratories currently available. One approach, common to all fields of the geosciences, but also in such diverse fields as philosophy, biology, linguistics, law, etc., is to utilise the analogue argumentation methodology. For the specific case of radioactive waste management, the term 'natural analogue' has taken on a particular meaning associated with providing supporting arguments for a repository safety assessment. This approach is discussed here with a brief overview of how the study of natural (and, in particular, geological) systems can provide supporting information on the likely long-term evolution of a deep geological waste repository. The overall approach is discussed and some relevant examples are presented, including the use of uranium ore bodies to assess waste form stability, the investigation of native metals to define the longevity of waste containers and how natural clays can provide information on the stability of waste tunnel backfill material. (authors)

Radioactive waste management solutions

International Nuclear Information System (INIS)

Siemann, Michael

2015-01-01

One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

Geologic modeling in risk assessment methodology for radioactive waste management

International Nuclear Information System (INIS)

Logan, S.E.; Berbano, M.C.

1977-01-01

Under contract to the U.S. Environmental Protection Agency (EPA), the University of New Mexico is developing a computer based assessment methodology for evaluating public health and environmental impacts from the disposal of radioactive waste in geologic formations. Methodology incorporates a release or fault tree model, an environmental model, and an economic model. The release model and its application to a model repository in bedded salt is described. Fault trees are constructed to provide the relationships between various geologic and man-caused events which are potential mechanisms for release of radioactive material beyond the immediate environs of the repository. The environmental model includes: 1) the transport to and accumulations at various receptors in the biosphere, 2) pathways from these environmental concentrations, and 3) radiation dose to man. Finally, economic results are used to compare and assess various disposal configurations as a basis for formulatin

Source term evaluation model for high-level radioactive waste repository with decay chain build-up.

Science.gov (United States)

Chopra, Manish; Sunny, Faby; Oza, R B

2016-09-18

A source term model based on two-component leach flux concept is developed for a high-level radioactive waste repository. The long-lived radionuclides associated with high-level waste may give rise to the build-up of activity because of radioactive decay chains. The ingrowths of progeny are incorporated in the model using Bateman decay chain build-up equations. The model is applied to different radionuclides present in the high-level radioactive waste, which form a part of decay chains (4n to 4n + 3 series), and the activity of the parent and daughter radionuclides leaching out of the waste matrix is estimated. Two cases are considered: one when only parent is present initially in the waste and another where daughters are also initially present in the waste matrix. The incorporation of in situ production of daughter radionuclides in the source is important to carry out realistic estimates. It is shown that the inclusion of decay chain build-up is essential to avoid underestimation of the radiological impact assessment of the repository. The model can be a useful tool for evaluating the source term of the radionuclide transport models used for the radiological impact assessment of high-level radioactive waste repositories.

Selection of the host rock for high level radioactive waste repository in China

International Nuclear Information System (INIS)

Jin Yuanxin; Wang Wenguang; Chen Zhangru

2001-01-01

The authors has briefly introduced the experiences of the host rock selection and the host rock types in other countries for high level radioactive waste repository. The potential host rocks in China are investigated. They include granite, tuff, clay, basalt, salt, and loess. The report has expounded the distributions, scale, thickness, mineral and chemical composition, construction, petrogenesis and the ages of the rock. The possibility of these rocks as the host rock has been studied. The six pieces of distribution map of potential rocks have been made up. Through the synthetical study, it is considered that granite as the host rock of high level radioactive waste repository is possible

[US Geological Survey research in radioactive waste disposal, fiscal year 1979:] Department of Energy program for locating and characterizing disposal sites

International Nuclear Information System (INIS)

Dixon, G.L.; Hoover, D.B.

1982-01-01

The objective was to locate and characterize rock masses at the NTS and in southern Nevada suitable to be host media for high-level radioactive wastes, to describe the areal and depth distribution and structural integrity of these rock masses, and to assess the potential for contaminant release by hydrologic transport or as a result of tectonic and (or) volcanic activity. From previous geologic work at NTS, the general geology is well known. Areas likely to have suitable host rocks and hydrologic conditions at depths appropriate for a repository are evaluated by detailed surface mapping, surface geophysical methods, exploratory drilling, and borehole geophysical techniques. Progress is reported. 5 refs., 1 fig

High-level waste processing at the Savannah River Site: An update

International Nuclear Information System (INIS)

Marra, J.E.; Bennett, W.M.; Elder, H.H.; Lee, E.D.; Marra, S.L.; Rutland, P.L.

1997-01-01

The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) in Aiken, SC mg began immobilizing high-level radioactive waste in borosilicate glass in 1996. Currently, the radioactive glass is being produced as a ''sludge-only'' composition by combining washed high-level waste sludge with glass frit. The glass is poured in stainless steel canisters which will eventually be disposed of in a permanent, geological repository. To date, DWPF has produced about 100 canisters of vitrified waste. Future processing operations will, be based on a ''coupled'' feed of washed high-level waste sludge, precipitated cesium, and glass frit. This paper provides an update of the processing activities completed to date, operational/flowsheet problems encountered, and programs underway to increase production rates

The potential of natural analogues in assessing systems for deep disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Chapman, N.A.; Smellie, J.A.T.

1984-08-01

Many of the processes which will lead to the breakdown of engineered barriers and the mobilisation of radionuclides in a deep waste repository have analogies in natural geological systems. These 'natural analogues' are seen as a particularly important means of validating predictive models, under the broad heading of radionuclide migration, which are used in long-term safety analyses. Their principal value is the opportunity they provide to examine processes occurring over geological timescales, hence allowing more confident extrapolation of short timescales experimental data. This report begins by reviewing the processes leading to breakdown of containment in a high-level radioactive waste repository in crystalline bedrock and the subsequent migration mechanisms for radionuclides back to the biosphere. Nine specific processes are identified as being of the most significance in migration models, based on available sensitivity analyses. Existing studies are assessed and possibilities considered for additional analogues. Conclusions are drawn for each process as to the extent to which analogues validate current predictions on scale and effect, longevity of function, etc. Where possible, quantitative evaluations are given, derived from analogue studies. A considerable amount of the information reviewed and presented could be used in the assessment of disposal of other waste types in other host rocks. (Auth.)

Prediction of long-term crustal movement for geological disposal of radioactive waste

International Nuclear Information System (INIS)

Sasaki, Takeshi; Morikawa, Seiji; Tabei, Kazuto; Koide, Hitoshi; Tashiro, Toshiharu

2000-01-01

Long-term stability of the geological environment is essential for the safe geological disposal of radioactive waste, for which it is necessary to predict the crustal movement during an assessment period. As a case study, a numerical analysis method for the prediction of crustal movement in Japan is proposed. A three-dimensional elastic analysis by FEM for the geological block structure of the Kinki region and the Awaji-Rokko area is presented. Stability analysis for a disposal cavern is also investigated. (author)

Economic appraisal of deployment schedules for high-level radioactive waste repositories

International Nuclear Information System (INIS)

Hoai Linh Doan, Phuong; Duquesnoy, T.; Devezeaux de Lavergne, J.G.

2017-01-01

The deep geological repository (DGR) is considered as the definitive management solution for high-level radioactive waste (HLW). Countries defined different DGR implementation schedules, depending on their national context and political choices. We raise the question of the economic grounds of such political decisions by providing an economic analysis of different DGR schedules. We investigate the optimal timing for DGR commissioning based on available Nuclear Energy Agency (NEA) data (2013). Two scenarios are considered: -1) rescheduling the deployment of a DGR with the same initial operational period, and -2) rescheduling the deployment of a DGR with a shorter operational period, i.e. initial closure date. Given the long timescales of such projects, we also take into account the discounting effect. The first finding is that it appears more economically favorable to extend the interim storage than to dispose of the HLW immediately. Countries which chose 'immediate' disposal are willing to accept higher costs to quickly solve the problem. Another interesting result is that there is an optimal solution with respect to the length of DGR operational period and the waste flow for disposal. Based on data provided by the Organisation for Economic Cooperation and Development (OECD)/Nuclear Energy Agency (NEA), we find an optimal operating period of about 15 years with a flow of 2000 tHM/year. (authors)