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Sample records for geological disposal contract

  1. Research on geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The aims of this research are to develop criteria for reviewing reliability and suitability of the result from Preliminary Investigations to be submitted by the implementer, and to establish a basic policy for safety review. For development of reliability and suitability criteria for reviewing the result of Preliminary Investigations, we evaluated the uncertainties and their influence from limited amount of investigations, as well as we identified important procedures during investigations and constructions of models, as follows: (1) uncertainties after limited amount of geological exploration and drilling, (2) influence of uncertainties in regional groundwater flow model, (3) uncertainties of DFN (Discrete Fracture Network) models in the fractured rock, (4) analyzed investigation methods described in implementer's report, and (5) identified important aspects in investigation which need to be reviewed and follow QA (Quality Assurance). For development of reliability and suitability criteria for reviewing the result of Detailed Investigations, we analyzed important aspects in investigation which supplies data to design and safety assessment, as well as studied the applicability of pressure interference data during excavation to verify hydrogeological model. Regarding the research for safety review, uncertainties of geologic process in long time-scale was studied. In FY2012, we started to evaluate the structural stabilities of concrete and bentonite in disposal environment. Finally, we continued to accumulate the knowledge on geological disposal into the database system. (author)

  2. Geological disposal concept hearings

    International Nuclear Information System (INIS)

    1996-01-01

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

  3. Research on geological disposal

    International Nuclear Information System (INIS)

    Uchida, Masahiro

    2011-01-01

    The aims of this research are to develop criteria for reviewing acceptability of the adequacy of the result of Preliminary and Detailed Investigations submitted by the implementor, and to establish a basic policy to secure safety for safety review. In FY 2010, 13 geology/climate related events for development of acceptance criteria for reviewing the adequacy of the result of Preliminary and Detailed Investigations were extracted. And the accuracy of geophysical exploration methods necessary for the Preliminary Investigation was evaluated. Regarding the research for safety review, we developed an idea of safety concept of Japanese geological disposal, and analyzed basic safety functions to secure safety. In order to verify the groundwater flow evaluation methods developed in regulatory research, the hydrological and geochemical data at Horonobe, northern Hokkaido were obtained, and simulated result of regional groundwater flow were compared with measured data. And we developed the safety scenario of geology/climate related events categorized by geological and geomorphological properties. Also we created a system to check the quality of research results in Japan and other countries in order to utilize for safety regulation, and developed a database system to compile them. (author)

  4. Geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    1979-01-01

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

  5. Geological disposal system development

    International Nuclear Information System (INIS)

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

    2000-04-01

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

  6. Geological disposal system development

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-04-01

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

  7. Engineering geology of waste disposal

    International Nuclear Information System (INIS)

    Bentley, S.P.

    1996-01-01

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

  8. Siting of geological disposal facilities

    International Nuclear Information System (INIS)

    1994-01-01

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

  9. Development of safety assessment method for human intrusion scenario in Japan. Part 1. Drilling scenario database for safety assessment of geological disposal (Contract research)

    International Nuclear Information System (INIS)

    Nagasawa, Hirokazu; Takeda, Seiji; Kimura, Hideo; Sasaki, Toshihisa

    2010-11-01

    In deep geological disposal or intermediate depth disposal, human intrusion, i.e. accidental excavation or drilling into the disposal site, may make a direct or an indirect effect on the disposal system. Safety assessment method for the human intrusion scenario, that is, the evaluation code of radiological effect from the human intrusion and the data to examine the reduction of the probability of the human intrusion occurring, is essential for the future safety regulation. Assuming that drilling action into the disposal site leads to the human proximity to the radioactive waste or the damage to the barrier system (drilling scenario), we have collected both the data on borehole drilling implemented in Japan and information on actual situation of drilling activities. Based on the data and information, we provide concrete exposure scenarios associated with borehole drilling in the vicinity of the repository and model for estimating the frequency on borehole reaching the depth of repository. The frequency is characterized with the relation to objective of excavation, geographical features, and region in Japan etc. We have developed an assembly of the information mentioned above as database, including the model parameters used in the code to assess radiation dose for drilling scenario. (author)

  10. Geological disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Sato, Tsutomu

    2000-01-01

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

  11. Evaluations for draft reports on geological disposal

    International Nuclear Information System (INIS)

    Maekawa, Keisuke; Igarashi, Hiroshi

    2002-10-01

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

  12. 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.)

  13. 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

  14. Safety assessment of HLW geological disposal system

    International Nuclear Information System (INIS)

    Naito, Morimasa

    2006-01-01

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

  15. 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)

  16. Geological disposal in the Belgian context

    International Nuclear Information System (INIS)

    Heremans, R.H.; Baetsle, L.H.

    1985-01-01

    The way of studying the high-level and α-bearing waste burial problem can vary from one country to another. In Belgium, if the electronuclear power represents about 60% of the total electricity production, the installed capacity is however limited to 5500 MWe. Furthermore, Belgium is a small country, densely populated, and its geology does not allow a large choice of underground formations acceptable for safe waste disposal. In 1974, site specific investigations were started on a 700 hectares area in the NE part of the country where Belgium's main nuclear research center and some nuclear fuel cycle facilities are located. The formation considered is a tertiary age clay layer underlying the Mol-Dessel area. Study and research works were organized in the frame of successive five year programs. The main objectives of the research are presented. After 10 years of intensive field, laboratory and desk work the obtained results allowed to start of the drafting of Preliminary Safety and Feasibility report in view of the construction of a demonstration facility. The project was performed by the CEN/SCK in the frame of shared financing contracts with the CEC and ONDRAF/NIRAS

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

    International Nuclear Information System (INIS)

    Masuda, Sumio; Sakuma, Hideki; Umeki, Hiroyuki

    2015-01-01

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

  18. Geological Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    Dody, A.; Klein, Ben; David, O.

    2014-01-01

    Disposal of radioactive waste imposes complicated constrains on the regulator to ensure the isolation of radioactive elements from the biosphere. The IAEA (1995) states that T he objective of radioactive waste management is to deal with radioactive waste in a manner that protects human health and the environment now and the future without imposing undue burdens on future generation . The meaning of this statement is that the operator of the waste disposal facilities must prove to the regulator that in routine time and in different scenarios the dose rate to the public will not exceed 0.3 mSv/y in the present and in the future up to 10,000 years

  19. Confidence building in implementation of geological disposal

    International Nuclear Information System (INIS)

    Umeki, Hiroyuki

    2004-01-01

    Long-term safety of the disposal system should be demonstrated to the satisfaction of the stakeholders. Convincing arguments are therefore required that instil in the stakeholders confidence in the safety of a particular concept for the siting and design of a geological disposal, given the uncertainties that inevitably exist in its a priori description and in its evolution. The step-wise approach associated with making safety case at each stage is a key to building confidence in the repository development programme. This paper discusses aspects and issues on confidence building in the implementation of HLW disposal in Japan. (author)

  20. 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

  1. The French geological disposal project CIGEO

    Energy Technology Data Exchange (ETDEWEB)

    Ouzounian, G. [ANDRA, Chatenay-Malabry cedex (France)

    2015-07-01

    This paper discusses the major management options for high level waste in France. Safety of the population and protection of the environment is the first priority. Reprocessing of used fuel and reuse of valuable material is considered. Reversible geological disposal (Cigéo Project) is the reference solution for the high-level waste.

  2. 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

  3. The Dutch geologic radioactive waste disposal project

    International Nuclear Information System (INIS)

    Hamstra, J.; Verkerk, B.

    1981-01-01

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

  4. Disposal of high level radioactive wastes in geological formations

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  5. Thermal loading effects on geological disposal

    International Nuclear Information System (INIS)

    Come, B.; Venet, P.

    1984-01-01

    A joint study on the thermal loading effects on geological disposal was carried out within the European Community Programme on Management and Storage of Radioactive Waste by several laboratories in Belgium, France and the Federal Republic of Germany. The purpose of the work was to review the thermal effects induced by the geological disposal of high-level wastes and to assess their consequences on the 'admissible thermal loading' and on waste management in general. Three parallel studies dealt separately with the three geological media being considered for HLW disposal within the CEC programme: granite (leadership: Commissariat a l'energie atomique (CEA), France), salt (leadership: Gesellschaft fuer Strahlen- und Umweltforschung (GSF), Federal Republic of Germany), and clay (leadership: Centre d'etude de l'energie nucleaire (CEN/SCK), Belgium). The studies were based on the following items: only vitrified high-level radioactive waste was considered; the multi-barrier confinement concept was assumed (waste glass, container (with or without overpack), buffer material, rock formation); the disposal was foreseen in a deep mined repository, in an 'in-land' geological formation; only normal situations and processes were covered, no 'accident' scenario being taken into account. Although reasonably representative of a wide variety of situations, the data collected and the results obtained are generic for granite, formation-specific for salt (i.e. related to the north German Zechstein salt formation), and site-specific for clay (i.e. concentrated on the Boom clay layer at the Mol site, Belgium). For each rock type, realistic temperature limits were set, taking into account heat propagation, thermo-mechanical effects inside the rock formations, induced or modified groundwater or brine movement, effects on the buffer material as well as effects on the waste glass and canister, and finally, nuclide transport

  6. Deep geological disposal research in Argentina

    International Nuclear Information System (INIS)

    Ninci Martinez, Carlos A.; Ferreyra, Raul E.; Vullien, Alicia R.; Elena, Oscar; Lopez, Luis E.; Maloberti, Alejandro; Nievas, Humberto O.; Reyes, Nancy C.; Zarco, Juan J.; Bevilacqua, Arturo M.; Maset, Elvira R.; Jolivet, Luis A.

    2001-01-01

    Argentina shall require a deep geological repository for the final disposal of radioactive wastes, mainly high-level waste (HLW) and spent nuclear fuel produced at two nuclear power plants and two research reactors. In the period 1980-1990 the first part of feasibility studies and a basic engineering project for a radioactive high level waste repository were performed. From the geological point of view it was based on the study of granitic rocks. The area of Sierra del Medio, Province of Chubut, was selected to carry out detailed geological, geophysical and hydrogeological studies. Nevertheless, by the end of the eighties the project was socially rejected and CNEA decided to stop it at the beginning of the nineties. That decision was strongly linked with the little attention paid to social communication issues. Government authorities were under a strong pressure from social groups which demanded the interruption of the project, due to lack of information and the fear it generated. The lesson learned was: social communication activities shall be carried out very carefully in order to advance in the final disposal of HLW at deep geological repositories (author)

  7. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    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) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS

  8. Demonstration of safety for geologic disposal

    International Nuclear Information System (INIS)

    Taylor, E.C.; Ramspott, L.D.; Sprecher, W.M.

    1994-01-01

    The US Department of Energy (DOE) is developing a nuclear waste management system that will accept high-level radioactive waste, transport it, store it, and ultimately emplace it in a deep geologic repository. The key activity now is determining whether Yucca Mountain, Nevada is suitable as a site for the repository. If so, the crucial technological advance will be the demonstration that disposal of nuclear waste will be safe for thousands of years after closure. This paper assesses the impact of regulatory developments, legal developments, and scientific developments on such a demonstration

  9. Mined Geologic Disposal System Concept of Operations

    International Nuclear Information System (INIS)

    Heidt, R.M.

    1995-01-01

    A Concept of Operations has been developed for the disposal of high-level radioactive waste in the potential geologic repository at Yucca Mountain. The Concept of Operations has been developed to document a cormion understanding of how the repository is to be operated. It is based on the repository architecture identified in the Initial Summary Report for Repository/Waste Package Advanced Conceptual Design and describes the operation of the repository from the initial receipt of waste through repository closure. Also described are operations for waste retrieval

  10. 2005 dossier: granite. Tome: phenomenological evolution of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

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

  11. Preliminary geological suitability assessment for LILW disposal

    International Nuclear Information System (INIS)

    Tomse, P.; Mele, I.

    2001-01-01

    Due to the growing need for a final disposal of LILW, the final solution for the short-lived LILW is the key issue of radioactive waste management in Slovenia at the moment. ARAO - the Slovenian Agency for Radwaste Management - is intensely involved in the re-initiated site selection process for a LILW repository. In this new process we are trying to combine as best as possible the technical, geologically-led and the advocacy-site selection processes. By a combination of technical and volunteer approach to the site selection we wish to guarantee high public involvement and sufficient flexibility of the process to adapt to specific conditions or new circumstances while the project is ongoing. In the technical phase, our tendency is to retain a larger number of potential areas/sites. We also keep open the possibility of choosing the type of repository. The decision between the surface and underground option will be made only once the site has been defined. In accordance with the IAEA recommendations the site selection process is divided into four stages: the conceptual and planning stage, area survey stage, site characterisation stage and site confirmation stage. Last year the area survey stage was started. In the preliminary geological suitability assessment the required natural predisposition of Slovene territory was assessed in order to locate geologically suitable formations. The assessment of natural conditions of the system was based on consideration of the main geological, hydro-geological and seismotectonic conditions. It was performed with ARC/INFO technology. The results are compiled in a map, showing potential areas for underground and surface disposal of LILW in Slovenia. It has been established that there is a potential suitability for both surface and underground disposal on about 10 000 km 2 of the Slovenian territory, which represents almost half of the entire Slovenian territory. These preliminary results are now being carefully re-examined. As an

  12. Submarine geologic disposal of nuclear waste

    International Nuclear Information System (INIS)

    Hollister, C.D.; Corliss, B.H.; Anderson, D.R.

    1980-01-01

    Site suitability characteristics of submarine geological formations for the disposal of radioactive wastes include the distribution coefficient of the host medium, permeability, viscoelastic nature of the sediments, influence of organic material on remobilization, and effects of thermal stress. The submarine geological formation that appears to best satisfy these criteria is abyssal ''red'' clay. Regions in the ocean that have coarse-grained deposits, high or variable thermal conductivity, high organic carbon content, and sediment thickness of less than 50 m are not being considered at this time. The optimum geological environment should be tranquil and have environmental predictability over a minimum of 10 5 years. Site selection activities for the North Atlantic and North Pacific are reviewed and future activities which include international cooperation are discussed. A paleoenvironmental model for Cenozoic sedimentation in the central North Pacific is presented based on studies of a long core from the Mid-Plate Gyre MPG-1 area, and is an example of the type of study that will be carried out in other seabed study areas. The data show that the MPG-1 region has been an area of slow, continuous accumulation during the past 65 million years. (author)

  13. Geology of the Integrated Disposal Facility Trench

    International Nuclear Information System (INIS)

    Reidel, Steve P.; Fecht, Karl R.

    2005-01-01

    This report describes the geology of the integrated Disposal Facility (IDF) Trench. The stratigraphy consists of some of the youngest sediments of the Missoula floods (younger than 770 ka). The lithology is dominated sands with minor silts and gravels that are largely unconsolidated. The stratigraphy can be subdivided into five geologic units that can be mapped throughout the trench. Four of the units were deposited by the Missoula floods and the youngest consists of windblown sand and silt. The sediment has little moisture and is consistent with that observed in the characterization boreholes. The sedimentary layers are flat lying and there are no faults or folds present. Two clastic dikes were encountered, one along the west wall and one that can be traced from the north to the southwall. The north-south clastic dike nearly bifurcates the trench but the west wall clastic dike can not be traced very far east into the trench. The classic dikes consist mainly of sand with clay-lined walls. The sediment in the dikes is compacted to partly cemented and are more resistant than the layered sediments

  14. 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)

  15. Geologic factors in nuclear waste disposal

    International Nuclear Information System (INIS)

    Towse, D.

    1978-07-01

    The study of geosciences and their relation to nuclear waste disposal and management entails analyzing the hydrology, chemistry, and geometry of the nuclear waste migration process. Hydrologic effects are determined by analyzing the porosity and permeability (natural and induced) of rock as well as pressures and gradients, dispersion, and aquifer length of the system. Chemistry parameters include radionuclide retardation factors and waste dissolution rate. Geometric parameters (i.e., parameters with dimension) evaluated include repository layer thickness, fracture zone area, tunnel length, and aquifer length. The above parameters act as natural barriers or controls to nuclear waste migration, and are evaluated in three potential geologic media: salt, shale, and crystalline rock deposits. Parametric values are assigned that correspond to many existing situations. These values, in addition to other important inputs, are lumped as a hydrology input into a computer simulation program used to model and calculate nuclear waste migration from the repository to the biosphere, and potential individual and population dose and radiation effects. These results are preliminary and show trends only; they do not represent an actual risk analysis

  16. 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.)

  17. Advances in Geologic Disposal System Modeling and Shale Reference Cases

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-09-22

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

  18. Study on the background information for the geological disposal concept

    International Nuclear Information System (INIS)

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

    2000-03-01

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

  19. 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

  20. 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

  1. Safety of geologic disposal of high level radioactive waste

    International Nuclear Information System (INIS)

    Zaitsu, Tomohisa; Ishiguro, Katsuhiko; Masuda, Sumio

    1992-01-01

    This article introduces current concepts of geologic disposal of high level radioactive waste and its safety. High level radioactive waste is physically stabilized by solidifying it in a glass form. Characteristics of deep geologic layer are presented from the viewpoint of geologic disposal. Reconstruction of multi-barrier system receives much attention to secure the safety of geologic disposal. It is important to research performance assessment of multi-barrier system for preventing dissolution or transfer of radionuclides into the ground water. Physical and chemical modeling for the performance assessment is outlined in the following terms: (1) chemical property of deep ground water, (2) geochemical modeling of artificial barrier spatial water, (3) hydrology of deep ground water, (4) hydrology of the inside of artificial barrier, and (5) modeling of radionuclide transfer from artificial barrier. (N.K.)

  2. Geological aspects of the nuclear waste disposal problem

    International Nuclear Information System (INIS)

    Laverov, N.P.; Omelianenko, B.L.; Velichkin, V.I.

    1994-06-01

    For the successful solution of the high-level waste (HLW) problem in Russia one must take into account such factors as the existence of the great volume of accumulated HLW, the large size and variety of geological conditions in the country, and the difficult economic conditions. The most efficient method of HLW disposal consists in the maximum use of protective capacities of the geological environment and in using inexpensive natural minerals for engineered barrier construction. In this paper, the principal trends of geological investigation directed toward the solution of HLW disposal are considered. One urgent practical aim is the selection of sites in deep wells in regions where the HLW is now held in temporary storage. The aim of long-term investigations into HLW disposal is to evaluate geological prerequisites for regional HLW repositories

  3. Study on the background information for the geological disposal concept

    International Nuclear Information System (INIS)

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

    1999-11-01

    Japan Nuclear Cycle Development Institute (JNC) has published the first R and D progress report in 1992. In which the fruits of the R and D works were compiled. Since then the next step of R and D has been developing progressively in Japan. Now JNC has a plan to make the second R and D progress report until before 2000, in which information on the geological disposal of high level radioactive waste(HLW) will be presented to show the technical reliability and technical basis to contribute for the site selection or the safety-standard developments. Recognizing the importance of the social consensus to the geological disposal of international discussions in 1990's, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. For getting social understanding and consensus, it is quite important to present the broad basis background information on the geological disposal of HLW, together with the technical basis and also the international discussion of the issues. In this report, the following studies have been done to help to prepare the background information for the 2nd R and D progress report, based on the recent informations and research and assessment works of last 2 years. These are, (1) As the part of general discussion, characteristics of HLW disposal and several issues to be considered for establishing the measures of the disposal of HLW were identified and analyzed from both practical and logical points of view. Those issues were the concept and image of the long term safety measures, the concept and criteria of geological disposal, and, safety assessment and performance assessment. (2) As the part of specific discussion, questions and concerns frequently raised by the non-specialists were taken up and 10 topics in relation to the geological disposal have been identified based on the discussion. Scientific and technical facts, consensus by the specialists on the issues, and international

  4. Explanation of ICRP publication 81 in consideration of geologic disposal

    International Nuclear Information System (INIS)

    Kosako, Toshiso; Sugiura, Nobuyuki; Yamamoto, Hideaki

    2003-01-01

    The International Commission on Radiological Protection which has published various recommendations on the radiation protection describes the system of radiation protection on the disposal of radioactive waste in Publication 46, 77 and 81. Especially, Publication 81, Radiation Protection Recommendations as Applied to the Disposal of Long-lived Solid Radioactive Waste, was published in order to supplement, update and clarify the material in Publication 46 published in 1985 in consideration of the recent international progress in the disposal of radioactive waste. At present, the study is in progress to materialize the concept and the safety regulation of geologic disposal in Japan, and it is important to reflect appropriately these international publications. This paper explains each paragraph in Publication 81 in order to understand the system of radiation protection on the geologic disposal fully and concretely, paying attention to the mutual relationship among each paragraph, the development of ICRP recommendations and the relationship to other publications. (author)

  5. The development of international safety standards on geological disposal

    International Nuclear Information System (INIS)

    McCartin, T.

    2005-01-01

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

  6. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  7. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

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

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

    International Nuclear Information System (INIS)

    Shiotsuki, Masao; Miyahara, Kaname

    2003-01-01

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

  9. 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

  10. 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

  11. Packaging radioactive wastes for geologic disposal

    International Nuclear Information System (INIS)

    Benton, H.A.

    1996-01-01

    The M ampersand O contractor for the DOE Office of Civilian Radioactive Waste Management is developing designs of waste packages that will contain the spent nuclear fuel assemblies from commercial and Navy reactor plants and various civilian and government research reactor plants, as well as high-level wastes vitrified in glass. The safe and cost effective disposal of the large and growing stockpile of nuclear waste is of national concern and has generated political and technical debate. This paper addresses the technical aspects of disposing of these wastes in large and robust waste packages. The paper discusses the evolution of waste package design and describes the current concepts. In addition, the engineering and regulatory issues that have governed the development are summarized and the expected performance in meeting the requirements are discussed

  12. 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

  13. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    1985-02-01

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

  14. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    1986-03-01

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

  15. International Collaboration Activities in Different Geologic Disposal Environments

    International Nuclear Information System (INIS)

    Birkholzer, Jens

    2015-01-01

    This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. Since 2012, in an effort coordinated by Lawrence Berkeley National Laboratory, UFD has advanced active collaboration with several international geologic disposal programs in Europe and Asia. Such collaboration allows the UFD Campaign to benefit from a deep knowledge base with regards to alternative repository environments developed over decades, and to utilize international investments in research facilities (such as underground research laboratories), saving millions of R&D dollars that have been and are being provided by other countries. To date, UFD's International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and national lab scientists associated with UFD have conducted specific collaborative R&D activities that align well with its R&D priorities.

  16. International Collaboration Activities in Different Geologic Disposal Environments

    Energy Technology Data Exchange (ETDEWEB)

    Birkholzer, Jens [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2015-09-01

    This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. Since 2012, in an effort coordinated by Lawrence Berkeley National Laboratory, UFD has advanced active collaboration with several international geologic disposal programs in Europe and Asia. Such collaboration allows the UFD Campaign to benefit from a deep knowledge base with regards to alternative repository environments developed over decades, and to utilize international investments in research facilities (such as underground research laboratories), saving millions of R&D dollars that have been and are being provided by other countries. To date, UFD’s International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and national lab scientists associated with UFD have conducted specific collaborative R&D activities that align well with its R&D priorities.

  17. 2005 dossier: clay. Tome: phenomenological evolution of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the phenomenological processes taking place in an argilite-type geologic disposal facility for high-level and long-lived (HLLL) radioactive wastes. Content: 1 - introduction: goal, input data, time and space scales, long-time forecasting of the phenomenological evolution; 2 - the Meuse/Haute-Marne site, the HLLL wastes and the disposal concepts: impact of the repository architecture; 3 - initial state of the geologic environment prior to the building up of the repository: general framework, geologic formations, tectonics and fractures, surface environment, geologic synthesis; 4 - phenomenological processes: storage-related processes, geodynamics-related processes, time scales of processes and of radionuclides migration, independence and evolution similarities of the repository and of the geologic environment; 5 - heat loads: heat transfers between containers and geologic formations, spatial organization of the thermal load, for C-type wastes and spent fuels, for B-type wastes, synthesis of the repository thermal load; 6 - flows and liquid solution and gas transfers: hydraulic behaviour of surrounding Jurassic formations (Tithonian, Kimmeridgian, Callovian, Oxfordian); 7 - chemical phenomena: chemical evolution of ventilated facilities (alveoles, galleries, boreholes), chemical evolution of B-type waste alveoles and of gallery and borehole sealing after closure, far field chemical evolution of Callovo-Oxfordian argilites and of other surrounding formations; 8 - mechanical evolution of the disposal and of the surrounding geologic environment: creation of an initial excavated damaged zone (EDZ), mechanical evolution of ventilated galleries, alveoles and sealing before and after closure, large-scale mechanical evolution; 9 - geodynamical evolution of the Callovo-Oxfordian and other surrounding formations and of the surface environment: internal

  18. Safeguarding of spent fuel conditioning and disposal in geological repositories

    International Nuclear Information System (INIS)

    Forsstroem, H.; Richter, B.

    1997-01-01

    Disposal of spent nuclear fuel in geological formations, without reprocessing, is being considered in a number of States. Before disposal the fuel will be encapsulated in a tight and corrosion resistant container. The method chosen for disposal and the design of the repository will be determined by the geological conditions and the very strict requirements on long-term safety. From a safeguards perspective spent fuel disposal is a new issue. As the spent fuel still contains important amounts of material under safeguards and as it can not be considered practicably irrecoverable in the repository, the IAEA has been advised not to terminate safeguards, even after closure of the repository. This raises a number of new issues where there could be a potential conflict of interests between safety and safeguards demands, in particular in connection with the safety principle that burdens on future generations should be avoided. In this paper some of these issues are discussed based on the experience gained in Germany and Sweden about the design and future operation of encapsulation and disposal facilities. The most important issues are connected to the required level of safeguards for a closed repository, the differences in time scales for waste management and safeguards, the need for verification of the fissile content in the containers and the possibility of retrieving the fuel disposed of. (author)

  19. Development of JNC geological disposal technical information integration system for geological environment field

    International Nuclear Information System (INIS)

    Tsuchiya, Makoto; Ueta, Shinzo; Ohashi, Toyo

    2004-02-01

    Enormous data on geology, geological structure, hydrology, geochemistry and rock properties should be obtained by various investigation/study in the geological disposal study. Therefore, 'JNC Geological Disposal Technical Information Integration System for Geological Environment Field' was developed in order to manage these data systematically and to support/promote the use of these data for the investigators concerned. The system is equipped with data base to store the information of the works and the background information of the assumptions built up in the works on each stage of data flow ('instigative', → 'data sampling' → interpretation' → conceptualization/modeling/simulation' → 'output') in the geological disposal study. In this system the data flow is shown as 'plan' composed of task' and 'work' to be done in the geological disposal study. It is possible to input the data to the database and to refer data from the database by using GUI that shows the data flow as 'plan'. The system was installed to the server computer possessed by JNC and the system utilities were checked on both the server computer and client computer also possessed by JNC. (author)

  20. Study on retrievability of waste package in geological disposal

    International Nuclear Information System (INIS)

    Hasegawa, Hiroshi; Noda, Masaru

    2002-02-01

    Retrievability of waste packages in geological disposal of high-level radioactive waste has been investigated from a technical aspect in various foreign countries, reflecting a social concern while retrievability is not provided as a technical requirement. This study investigates the concept of reversibility and retrievability in foreign countries and a technical feasibility on retrievability of waste packages in the geological disposal concept shown in the H12 report. The conclusion obtained through this study is as follows: 1. Concept of reversibility and retrievability in foreign countries. Many organizations have reconsidered the retrievability as one option in the geological disposal to improve the reversibility of the stepwise decision-making process and provide the flexibility, even based upon the principle of the geological disposal that retrieval of waste from the repository is not intended. 2. Technical feasibility on the retrievability in disposal concept in the H12 report. It is confirmed to be able to remove the buffer and to retrieve the waste packages by currently available technologies even after the stages following emplacement of the buffer. It must be noted that a large effort and expense would be required for some activities such as the reconstruction of access route if the activities started after a stage of backfilling disposal tunnels. 3. Evaluation of feasibility on the retrievability and extraction of the issues. In the near future, it is necessary to study and confirm the practical workability and economical efficiency for the retrieving method of waste packages proposed in this study, the handling and processing method of removed buffer materials, and the retrieving method of waste packages in the case of degrading the integrity of waste packages or not emplacing the waste packages in the assumed attitude, etc. (author)

  1. 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

  2. Draft Geologic Disposal Requirements Basis for STAD Specification

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-03-25

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

  3. 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)

  4. 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

  5. Geological aspects of the deep disposal of radioactive waste

    International Nuclear Information System (INIS)

    McEwen, T.J.

    1998-01-01

    Various environments have been selected throughout the world for the potential deep disposal of long-lived radioactive waste. The selection of these environments has been carried out using a variety of methods, some of them more logical and defensible than others. The 'raison d'etre' for their selection also varies from country to country. Important lessons have been learnt from the site selection programmes, the site characterisation activities and the accompanying performance assessments that have been carried out concerning the suitability of geological environments for the disposal of long-lived waste. These lessons are the subject of this paper. 24 refs

  6. 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)

  7. Deep geological disposal of radioactive waste - An international perspective

    Energy Technology Data Exchange (ETDEWEB)

    Gautschi, A. [National Cooperative for the Disposal of Radioactive Waste (NAGRA), Wettingen (Switzerland)

    2015-07-01

    This article provides a condensed summary of a presentation given by the author in June 2015. Various types of disposal facilities are reviewed, ranging from very limited natural barriers through to sophisticated, multi-barrier systems. Advantages, disadvantages and costs of the various disposal options are discussed. In particular, solutions used worldwide are listed in a comprehensive table. The simpler solutions range from open, non-engineered barriers through to simple geological barriers on the surface and underground. Multi-barrier systems in Sweden, Finland, France, Switzerland and Canada are listed and discussed. These include geological barriers through to engineered confinements in crystalline and sedimentary rocks. Links to relevant internet web sites are quoted.

  8. Deep geological disposal of radioactive waste - An international perspective

    International Nuclear Information System (INIS)

    Gautschi, A.

    2015-01-01

    This article provides a condensed summary of a presentation given by the author in June 2015. Various types of disposal facilities are reviewed, ranging from very limited natural barriers through to sophisticated, multi-barrier systems. Advantages, disadvantages and costs of the various disposal options are discussed. In particular, solutions used worldwide are listed in a comprehensive table. The simpler solutions range from open, non-engineered barriers through to simple geological barriers on the surface and underground. Multi-barrier systems in Sweden, Finland, France, Switzerland and Canada are listed and discussed. These include geological barriers through to engineered confinements in crystalline and sedimentary rocks. Links to relevant internet web sites are quoted

  9. 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.)

  10. Reversibility and retrievability in geologic disposal of radioactive waste

    International Nuclear Information System (INIS)

    2001-01-01

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

  11. Development of NUMO safety case for geological disposal

    International Nuclear Information System (INIS)

    Suzuki, Satoru; Deguchi, Akira

    2016-01-01

    NUMO has developed a generic safety ease based on the latest knowledge to show the feasibility and safety of geological disposal in Japan. The NUMO safety case has been developed to provide a basic structure for subsequent safety cases that would be applied to any selected site, emphasising practical approaches and methodology, which will be applicable for the conditions/constraints during an actual siting process. This paper will provide a brief overview of the NUMO safety case. (author)

  12. Interface management for the Mined Geologic Disposal System

    International Nuclear Information System (INIS)

    Ashlock, K.J.

    1998-03-01

    The purpose of this paper is to present the interface management process that is to be used for Mined Geologic Disposal System (MGDS) development. As part of the systems engineering and integration performed on the Yucca Mountain Project (YMP), interface management is critical in the development of the potential MGDS. The application of interface management on the YMP directly addresses integration between physical elements of the MGDS and the organizations responsible for their development

  13. Human intruder dose assessment for deep geological disposal

    International Nuclear Information System (INIS)

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

    2013-07-01

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

  14. The computational design of Geological Disposal Technology Integration System

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Iwamoto, Hiroshi; Kobayashi, Shigeki; Neyama, Atsushi; Endo, Shuji; Shindo, Tomonori

    2002-03-01

    In order to develop 'Geological Disposal Technology Integration System' that is intended to systematize as knowledge base for fundamental study, the computational design of an indispensable database and image processing function to 'Geological Disposal Technology Integration System' was done, the prototype was made for trial purposes, and the function was confirmed. (1) Database of Integration System which systematized necessary information and relating information as an examination of a whole of repository composition and managed were constructed, and the system function was constructed as a system composed of image processing, analytical information management, the repository component management, and the system security function. (2) The range of the data treated with this system and information was examined, the design examination of the database structure was done, and the design examination of the image processing function of the data preserved in an integrated database was done. (3) The prototype of the database concerning a basic function, the system operation interface, and the image processing function was manufactured to verify the feasibility of the 'Geological Disposal Technology Integration System' based on the result of the design examination and the function was confirmed. (author)

  15. New safety concept for geological disposal in Japan - -16339

    International Nuclear Information System (INIS)

    Kitayama, Kazumi

    2009-01-01

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

  16. Study on the development of safety regulations for geological disposal of high-level radioactive waste

    International Nuclear Information System (INIS)

    Wei Fangxin

    2012-01-01

    The development of regulations under Regulations on Safety Management of Radioactive Waste has become necessary as the issuance of it. The regulations related to geological disposal of high-level radioactive waste can promote the progress of research and development on geological disposal of high-level radioactive waste in China. This paper has present suggestions on development of regulations on geological disposal of high-level radioactive waste by analyzing development of safety regulations on geological disposal of high-level radioactive waste in foreign countries and problems occurred in China and discussed important issues related to the development of safety regulations on geological disposal of high-level radioactive waste. (author)

  17. 2005 dossier: granite. Tome: safety analysis of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

  18. Retrievability in the Deep Geological Disposal motivation and implications

    International Nuclear Information System (INIS)

    Fernandez Polo, J. J.; Aneiros, J. M.; Alonso, J.

    2000-01-01

    The final disposal of High Level Wastes (HLW) in a repository without the intention of retrieval has been the conceptual basis used by most countries to define their deep geological disposal concepts. As a result, current disposal concepts allow, but do not facilitate, the retrieval of the waste. The concept of retrievability has been introduced in the stepwise development process of the deep geological disposal for a series of ethical, socio-political, and technological reasons, which have structured a great deal of attention in the international community. At present, although no clear definition has been given to the term retrievability there seems to be a general consensus in respect of its interpretation as the capacity to retrieve waste from the underground facilities of the repository up to several years after its closure. The retrieval of the HLW packages from the disposal cells entails tackling a series of technological and operational constraints stemming, on the one hand, from the configuration and state of the repository at the time of retrieval and, on the other, from the environmental conditions of temperature and radiation in which such operations have to be carried out. Most countries, Spain included, are assessing the technical feasibility of retrieving waste during the different stages of the repository lifetime, exploring at the same time the possibility of implementing some changes in the repository's design, construction and operation without affecting its long-term safety. The purpose of this paper is three-fold (1) to identify the motivations that have led the international community to consider retrievability in the repository's stepwise development process, (2) to analyse, qualitatively, the different implications this has on current repository concepts, and (3) to state the current Spanish position. (Author)

  19. 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)

  20. 2005 dossier: clay. Tome: safety evaluation of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of an argilite-type geologic disposal facility for high-level and long-lived (HLLL) radioactive wastes. Content: 1 - safety approach: context and general goals, general safety principles, specificity of the argilite repository safety approach, general approach; 2 - general description: HLLL wastes, geologic context of the Meuse/Haute-Marne site, repository architecture; 3 - safety functions and disposal design: time and space scales, safety approach by functions, functional analysis methodology, analysis of safety functions during the construction, exploitation and observation phases, safety functions analysis during post-closure phase; 4 - operational safety: dosimetric evaluation, risk analysis (explosible gases, fire hazards, lift cage drop, container drop); 5 - long-term efficiency of the disposal facility: normal evolution scenario, from conceptual models to the safety calculation model, description of the safety model, quantitative evaluation of the normal evolution scenario, main lessons learnt from the efficiency analysis; 6 - management of uncertainties: identification, building up of altered situations, mastery of uncertainties; 7 - evaluation of altered evolution scenarios: sealing defect scenario, container defect scenario, drilling scenario, strongly degraded operation scenario; 8 - conclusions: lessons learnt, possible improvements. (J.S.)

  1. A new procedure for implementing a geological disposal

    International Nuclear Information System (INIS)

    Anon.

    2014-01-01

    The British government has launched a new procedure for selecting and implementing a geological disposal. This procedure is based on long-term cooperation with municipalities that wish to home this facility. In a preliminary 2 year long step, a national geological survey will be performed in order to determine regions that are suitable to home a geological disposal. Then discussions between municipalities that are voluntary and the enterprise in charge of developing the project will begin. Municipalities will receive an investment up to 1 million pounds a year in the first years of the selecting procedure and then 2.5 million pounds a year when discussions become more formal. British authorities consider that the procedure for selecting a site may last up to 20 years. A previous attempt to find a site failed in 2013 when 2 regions that had been interested in the project since 2008, were finally rebuffed by the regional council that opposed the project. Scotland and Wales have their own strategy for the management of radioactive waste. (A.C.)

  2. The Suitable Geological Formations for Spent Fuel Disposal in Romania

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  3. 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

  4. Nuclear waste and a deep geological disposal facility

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  5. Solving the geologic issues in nuclear waste disposal

    International Nuclear Information System (INIS)

    Towse, D.

    1979-01-01

    Technical problems with nuclear waste disposal are largely geological. If these are not solved, curtailment of nuclear power development may follow, resulting in loss of an important element in the national energy supply. Present knowledge and credible advances are capable of solving these problems provided a systems view is preserved and a national development plan is followed. This requires identification of the critical controllable elements and a systematic underground test program to prove those critical elements. Waste migration can be understood and controlled by considering the key elements in the system: the system geometry, the hydrology, and the waste-rock-water chemistry. The waste program should: (1) identify and attack the critical problems first; (2) provide tests and demonstration at real disposal sites; and (3) schedule elements with long lead-times for early start and timely completion

  6. The EVEREST project: sensitivity analysis of geological disposal systems

    International Nuclear Information System (INIS)

    Marivoet, Jan; Wemaere, Isabelle; Escalier des Orres, Pierre; Baudoin, Patrick; Certes, Catherine; Levassor, Andre; Prij, Jan; Martens, Karl-Heinz; Roehlig, Klaus

    1997-01-01

    The main objective of the EVEREST project is the evaluation of the sensitivity of the radiological consequences associated with the geological disposal of radioactive waste to the different elements in the performance assessment. Three types of geological host formations are considered: clay, granite and salt. The sensitivity studies that have been carried out can be partitioned into three categories according to the type of uncertainty taken into account: uncertainty in the model parameters, uncertainty in the conceptual models and uncertainty in the considered scenarios. Deterministic as well as stochastic calculational approaches have been applied for the sensitivity analyses. For the analysis of the sensitivity to parameter values, the reference technique, which has been applied in many evaluations, is stochastic and consists of a Monte Carlo simulation followed by a linear regression. For the analysis of conceptual model uncertainty, deterministic and stochastic approaches have been used. For the analysis of uncertainty in the considered scenarios, mainly deterministic approaches have been applied

  7. 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

  8. 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

  9. 2005 dossier: granite. Tome: architecture and management of the geologic disposal

    International Nuclear Information System (INIS)

    2005-01-01

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

  10. Towards transparent, proportionate and deliverable regulation for geological disposal

    International Nuclear Information System (INIS)

    2010-01-01

    As part of its activities, the Regulators' Forum of the NEA Radioactive Waste Management Committee has been examining the regulatory criteria for the long-term performance of geological disposal. In this context, it organised a workshop entitled 'Towards Transparent, Proportionate and Deliverable Regulation for Geological Disposal', which served to verify current status and needs. Participants included regulators, implementers, policy makers, R and D specialists and academics. Themes addressed included duties to future generations, timescales for regulation, stepwise decision making, roles of optimisation and best available techniques (BAT), multiple lines of reasoning, safety and performance indicators, recognition of uncertainties and the importance of stakeholder interactions. The workshop highlighted the significant amount of work accomplished over the past decade, but also identified important differences between national regulations even if these are not in contradiction with international guidance. Also highlighted was the importance of R and D carried out on behalf of the regulator. In addition to the contributed papers, these proceedings trace the numerous discussions that formed an integral part of the workshop. They constitute an important and unique documentary basis for researchers and radioactive waste management specialists

  11. Implementing geological disposal. A long-term governance challenge

    Energy Technology Data Exchange (ETDEWEB)

    Bergmans, Anne [Antwerp Univ. (Belgium). Faculty of Political and Social Sciences and Faculty of Law

    2015-07-01

    Calling geological disposal (GD) a technical and societal challenge and arguing that democratic decision-making on GD requires public and stakeholder engagement (PSE), are statements that will not meet much opposition. A process of 'governance' consists of engaging stakeholder groups in decision making processes and contrasts with more traditional, often technocratic forms of government. As will be argued in other papers in this conference (e.g. Grunwald; Kallenbach-Herbert et al.; Roehlig et al.) it is of fairly recent date, that concerned actors increasingly recognize that PSE should relate to both the societal and technical questions concerning GD. While most people would agree in theory, putting 'technical democracy' (Callon et al. 2001) in practice, often proofs to be less obvious. Opening up the technical 'black box' remains a crucial challenge in discussing the implications of GD for society and for the environment. As findings from the InSOTEC project show, this can be explained because different types of problematization occur, often considered as sequential, rather than intertwined (Barthe et al. 2014). Social problematization of GD, i.e. considering the remaining obstacles for implementation to be in essence social in nature, is often associated with the siting stage, when the technological project meets its social environment (ibidem). Formal participatory processes are often aimed mainly at dealing with socio-economic impacts and adapting life on the surface to the underground technology project, rather than the other way around (Bergmans et al. forthcoming). Still such interactions can, and have indeed proven to, lead to technical problematization, i.e. putting into question the technical project or certain aspects of it (cf. Barthe et al. 2014), by concerned stakeholders. As can be observed in the case of Sweden - for GD of spent fuel, and Belgium - for surface disposal of low- and intermediate level waste, this does not

  12. Implementing geological disposal. A long-term governance challenge

    International Nuclear Information System (INIS)

    Bergmans, Anne

    2015-01-01

    Calling geological disposal (GD) a technical and societal challenge and arguing that democratic decision-making on GD requires public and stakeholder engagement (PSE), are statements that will not meet much opposition. A process of 'governance' consists of engaging stakeholder groups in decision making processes and contrasts with more traditional, often technocratic forms of government. As will be argued in other papers in this conference (e.g. Grunwald; Kallenbach-Herbert et al.; Roehlig et al.) it is of fairly recent date, that concerned actors increasingly recognize that PSE should relate to both the societal and technical questions concerning GD. While most people would agree in theory, putting 'technical democracy' (Callon et al. 2001) in practice, often proofs to be less obvious. Opening up the technical 'black box' remains a crucial challenge in discussing the implications of GD for society and for the environment. As findings from the InSOTEC project show, this can be explained because different types of problematization occur, often considered as sequential, rather than intertwined (Barthe et al. 2014). Social problematization of GD, i.e. considering the remaining obstacles for implementation to be in essence social in nature, is often associated with the siting stage, when the technological project meets its social environment (ibidem). Formal participatory processes are often aimed mainly at dealing with socio-economic impacts and adapting life on the surface to the underground technology project, rather than the other way around (Bergmans et al. forthcoming). Still such interactions can, and have indeed proven to, lead to technical problematization, i.e. putting into question the technical project or certain aspects of it (cf. Barthe et al. 2014), by concerned stakeholders. As can be observed in the case of Sweden - for GD of spent fuel, and Belgium - for surface disposal of low- and intermediate level waste, this does not

  13. Geological Disposal of Radioactive Waste: Technological Implications for Retrievability

    International Nuclear Information System (INIS)

    2009-01-01

    Various IAEA Member States are discussing whether and to what degree reversibility (including retrievability) might be built into management strategies for radioactive waste. This is particularly the case in relation to the disposal of long lived and/or high level waste and spent nuclear fuel (SNF) in geological repositories. It is generally accepted that such repositories should be designed to be passively safe with no intention of retrieving the waste. Nevertheless, various reasons have been advanced for including the concept of reversibility and the ability to retrieve the emplaced wastes in the disposal strategy. The intention is to increase the level of flexibility and to provide the ability to cope with, or to benefit from, new technical advances in waste management and materials technologies, and to respond to changing social, economic and political opinion. The technological implications of retrievability in geological disposal concepts are explored in this report. Scenarios for retrieving emplaced waste packages are considered and the report aims to identify and describe any related technological provisions that should be incorporated into the design, construction, operational and closure phases of the repository. This is based on a number of reference concepts for the geological disposal of radioactive waste (including SNF) which are currently being developed in Member States with advanced development programmes. The report begins with a brief overview of various repository concepts, starting with a summary of the types of radioactive waste that are typically considered for deep geological disposal. The main host rocks considered are igneous crystalline and volcanic rocks, argillaceous clay rocks and salts. The typical design features of repositories are provided with a description of repository layouts, an overview of the key features of the major repository components, comprising the waste package, the emplacement cells and repository access facilities

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

    International Nuclear Information System (INIS)

    Anderson, D.R.

    1979-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, D.R.

    1979-05-01

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

  16. Site selection and design basis of the National Disposal Facility for LILW. Geological and engineering barriers

    International Nuclear Information System (INIS)

    Boyanov, S.

    2010-01-01

    Content of the presentation: Site selection; Characteristics of the “Radiana” site (location, geological structure, physical and mechanical properties, hydro-geological conditions); Design basis of the Disposal Facility; Migration analysis; Safety assessment approach

  17. Geological disposal of high-level radioactive waste and geological environment in Japan

    International Nuclear Information System (INIS)

    Shimizu, Kazuhiko; Seo, Toshihiro; Yshida, Hidekazu

    2001-01-01

    The geological environment has two main functions in terms of ensuring the safety of geological disposal of high-level radioactive waste. One relates to the fundamental long-term stability of the site and the other to the properties of the host rock formations and groundwaters which facilitate the emplacement of the engineered barrier system and act as a natural barrier. In this connection, the feasibility of selecting a geological environment in Japan which is appropriate for geological disposal was discussed, based on findings obtained from case studies and field measurements. Considering long-term stability of the site, it is important to understand the effects and spatial distributions of the natural phenomena such as fault movement, volcanic activity, uplift/denudation and climatic/sea-level changes. Fault movement and volcanic activity are relatively localized phenomena, and can be avoided by considering only areas that are sufficiently remote from existing volcanoes and major active faults for these phenomena to have a negligible probability of causing significant effects. Uplift/denudation and climatic/sea-level changes are gradual phenomena and are more ubiquitous. It is, nevertheless, possible to estimate future trends by extrapolating the past changes into the future, and then to identify areas that may not be affected significantly by such phenomena. Considering the properties of the host rocks and groundwaters, it can be understood, from the presently available data, that deep groundwater in Japan generally flows slowly and its chemistry is in a reduced state. The data also suggest that deep rock masses, where the ground temperature is acceptably low and the rock pressure is almost homogeneous, are widely located throughout Japan. Based on the examination of the geological environment in Japan, it is possible to discuss the requirements for the geological environment to be considered and the investigations to be performed during the site selection

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  19. Deep Geologic Nuclear Waste Disposal - No New Taxes - 12469

    Energy Technology Data Exchange (ETDEWEB)

    Conca, James [RJLee Group, Inc., Pasco WA 509.205.7541 (United States); Wright, Judith [UFA Ventures, Inc., Richland, WA (United States)

    2012-07-01

    To some, the perceived inability of the United States to dispose of high-level nuclear waste justifies a moratorium on expansion of nuclear power in this country. Instead, it is more an example of how science yields to social pressure, even on a subject as technical as nuclear waste. Most of the problems, however, stem from confusion on the part of the public and their elected officials, not from a lack of scientific knowledge. We know where to put nuclear waste, how to put it there, how much it will cost, and how well it will work. And it's all about the geology. The President's Blue Ribbon Commission on America's Nuclear Future has drafted a number of recommendations addressing nuclear energy and waste issues (BRC 2011) and three recommendations, in particular, have set the stage for a new strategy to dispose of high-level nuclear waste and to manage spent nuclear fuel in the United States: 1) interim storage for spent nuclear fuel, 2) resumption of the site selection process for a second repository, and 3) a quasi-government entity to execute the program and take control of the Nuclear Waste Fund in order to do so. The first two recommendations allow removal and storage of spent fuel from reactor sites to be used in the future, and allows permanent disposal of actual waste, while the third controls cost and administration. The Nuclear Waste Policy Act of 1982 (NPWA 1982) provides the second repository different waste criteria, retrievability, and schedule, so massive salt returns as the candidate formation of choice. The cost (in 2007 dollars) of disposing of 83,000 metric tons of heavy metal (MTHM) high-level waste (HLW) is about $ 83 billion (b) in volcanic tuff, $ 29 b in massive salt, and $ 77 b in crystalline rock. Only in salt is the annual revenue stream from the Nuclear Waste Fund more than sufficient to accomplish this program without additional taxes or rate hikes. The cost is determined primarily by the suitability of the geologic

  20. Development and improvement of safety analysis code for geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In order to confirm the long-term safety concerning geological disposal, probabilistic safety assessment code and other analysis codes, which can evaluate possibility of each event and influence on engineered barrier and natural barrier by the event, were introduced. We confirmed basic functions of those codes and studied the relation between those functions and FEP/PID which should be taken into consideration in safety assessment. We are planning to develop 'Nuclide Migration Assessment System' for the purpose of realizing improvement in efficiency of assessment work, human error prevention for analysis, and quality assurance of the analysis environment and analysis work for safety assessment by using it. As the first step, we defined the system requirements and decided the system composition and functions which should be mounted in them based on those requirements. (author)

  1. Risk methodology for geologic disposal of radioactive waste: interim report

    International Nuclear Information System (INIS)

    Campbell, J.E.; Dillon, R.T.; Tierney, M.S.; Davis, H.T.; McGrath, P.E.; Pearson, F.J. Jr.; Shaw, H.R.; Helton, J.C.; Donath, F.A.

    1978-10-01

    The Fuel Cycle Risk Analysis Division of Sandia Laboratories is funded by the Nuclear Regulatory Commission (NRC) to develop a methodology for assessment of the long-term risks from radioactive waste disposal in deep, geologic media. The first phase of this work, which is documented in this report, involves the following: (1) development of analytical models to represent the processes by which radioactive waste might leave the waste repository, enter the surface environment and eventually reach humans and (2) definition of a hypothetical ''reference system'' to provide a realistic setting for exercise of the models in a risk or safety assessment. The second phase of this work, which will be documented in a later report, will involve use of the analytical models in a demonstration risk or safety assessment of the reference system. The analytical methods and data developed in this study are expected to form the basis for a portion of the NRC repository licensing methodology

  2. Deep geologic disposal. Lessons learnt from recent performance assessment studies

    International Nuclear Information System (INIS)

    Pescatore, C.; Andersson, J.

    1998-01-01

    Performance assessment (PA) studies are part of the decision basis for the siting, operation, and closure of deep repositories of long-lived nuclear wastes. In 1995 the NEA set up the Working Group on Integrated Performance Assessments of Deep Repositories (IPAG) with the goals to analyse existing PA studies, learn about what has been produced to date, and shed light on what could be done in future studies. Ten organisations submitted their most recent PA study for analysis and discussion, including written answers to over 70 questions. Waste management programmes, disposal concepts, geologies, and different types and amounts of waste offered a unique opportunity for exchanging information, assessing progress in PA since 1990, and identifying recent trends. A report was completed whose main lessons are overviewed. (author)

  3. Interface management for the Mined Geologic Disposal System

    International Nuclear Information System (INIS)

    Ashlock, K.J.; Sellers, M.D.

    1998-01-01

    The Management and Operations (M and O) contractor for the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) program exists to support DOE in the successful development and operation of an integrated system to manage the nation's spent nuclear fuel and high-level wastes. As part of the system engineering and integration performed on the Yucca Mountain Project (YMP), interface management is critical in the development of the Mined Geologic Disposal System (MGDS). The application of interface management on the YMP directly addresses integration between physical elements of the MGDS and the organizations responsible for their development. An initiative to utilize interface management and the interface control document development process for organizational interfaces is also being pursued to help ensure consistent use of information by multiple organizations

  4. Treatment of uncertainties in the geologic disposal of radioactive waste

    International Nuclear Information System (INIS)

    Cranwell, R.M.

    1985-01-01

    Uncertainty in the analysis of geologic waste disposal is generally considered to have three primary components: (1) computer code/model uncertainty, (2) model parameter uncertainty, and (3) scenario uncertainty. Computer code/model uncertainty arises from problems associated with determination of appropriate parameters for use in model construction, mathematical formulatin of models, and numerical techniques used in conjunction with the mathematical formulation of models. Model parameter uncertainty arises from problems associated with selection of appropriate values for model input, data interpretation and possible misuse of data, and variation of data. Scenario uncertainty arises from problems associated with the ''completeness' of scenarios, the definition of parameters which describe scenarios, and the rate or probability of scenario occurrence. The preceding sources of uncertainty are discussed below

  5. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. An extra issue: background of the 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 geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, an extra issue of the progress report, was prepared for the expected readers of the report to have background information on the geological disposal. Thus it gives information about (1) generation of high-level radioactive wastes, (2) history of plans proposed for HLW disposal in Japan, and (3) procedure until the geological disposal plan is finally adopted and basic future schedules. It further discusses on such problems in HLW treatment and disposal, as for example a problem of reliable safety for a very long period. (Ohno, S.)

  6. A new look on the safety case for geologic disposal

    International Nuclear Information System (INIS)

    Pescatore, Claudio; Riotte, Hans; Voinis, Sylvie

    2005-01-01

    It has become evident that the development of a geologic repository will involve a number of stages punctuated by interdependent decisions on whether and how to move to the next stage. These decisions require a clear and traceable presentation of technical and scientific arguments that will help in giving confidence in the feasibility and safety of a proposed concept. A detailed safety assessment is typically required at major decision points in repository planning and implementation, including decisions that require the granting of licenses. In recent years the scope of the safety assessment has broadened to include the collation of a broad range of evidence and arguments that complement and support the reliability of the results of quantitative analyses, and the broader term 'post-closure safety case' or simply 'safety case' is used to refer to these studies. This paper reflects the historical development from integrated safety assessment to modern safety cases and outlines the main elements of a safety case for geologic disposal. The presentation of the safety strategy, multiple barrier concept and strategies to deal with uncertainties are analysed and the importance of an explicit statement of confidence is emphasized. (author)

  7. New guidelines for geological disposal of nuclear waste in Sweden

    International Nuclear Information System (INIS)

    Dverstorp, B.; Wiebert, A.; Jensen, M.

    2008-01-01

    In its recently issued guidance on geological disposal of spent nuclear fuel and nuclear waste the Swedish Radiation Protection Authority (SSI) develops the concepts of the regulatory risk target, best available technique (BAT) and optimisation, and gives recommendations on how to demonstrate compliance with SSI's regulations for different time periods after closure of a geological repository. Because a post-closure risk analysis will always be associated with inescapable uncertainties, the application of BAT is seen as an important complementary requirement to risk calculations. The guidance states that the implementer should be able to motivate all important choices and decisions during the development of a repository, including siting, design, construction and operation, in relation to the repository's long-term protective capability. Although the risk target is in principle independent of time, i.e. the basic premise is that future generations should be given the same protection as today generation, the guidance acknowledges the increasing difficulty of making meaningful assessments of risk in the distant future. This is reflected in a differentiated expectation in the reporting of compliance arguments: for long-time periods after closure (beyond 100 000 years) more emphasis is given on robust measures of repository performance than on calculated risks that are based on speculative assumptions on, e.g. future climate and human society. (authors)

  8. The safe disposal of radioactive wastes in geologic salt formations

    International Nuclear Information System (INIS)

    Kuehn, K.; Proske, R.

    Geologic salt formations appear to be particularly suitable for final storage. Their existance alone - the salt formations in Northern Germany are more than 200 million years old - is proof of their stability and of their isolation from biological cycles. In 1967 the storage of LAW and later, in 1972, of MAW was started in the experimental storage area Asse, south-east of Braunschweig, after the necessary technical preparations had been made. In more than ten years of operation approx. 114,000 drums of slightly active and 1,298 drums of medium-active wastes were deposited without incident. Methods have been developed for filling the available caverns with wastes and salt to ensure the security of long term disposal without supervision. Tests with electric heaters for simulation of heat-generating highly active wastes confirm the good suitability of salt formations for storing these wastes. Safety analyses for the operating time as well as for the long term phase after closure of the final storage area, which among others also comprise the improbable ''greatest expected accident'', namely break through of water, are carried out and confirm the safety of ultimate storage of radioactive wastes in geological salt formations. (orig./HP) [de

  9. Office of Geologic Repositories issues hierarchy for a mined geologic disposal system

    International Nuclear Information System (INIS)

    1987-08-01

    The Nuclear Regulatory Commission (NRC) has indicated that the identification of the issues that must be resolved to complete licensing assessments of site and design suitability is an important step in the licensing process. The issues hierarchy developed by the Office of Geologic Repositories (OGR) for the mined geologic disposal system (MGDS) are based on the issues-hierarchy concept presented in the Mission Plan. Specific questions are encompassed by the general issue statements in the OGR issues hierarchy. The OGR issues hierarchy is limited to the issues related to the siting and licensing requirements of applicable federal regulations and does not address the requirements of other regulations, functional or operating requirements for the MGDS, or requirements for the integration and the design/operational efficiency of the MGDS. 4 figs

  10. 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

  11. 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)

  12. 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)

  13. Uncertainties in the geological disposal for high-level radioactive waste

    International Nuclear Information System (INIS)

    Liu Xiaodong; Wang Changxuan

    2008-01-01

    Geological disposal, referring to the disposal of high-level solid radioactive waste in a facility located underground in a stable geological formation, was considered the most favourable methods to provide long term isolation of the radionuclides in the waste from the biosphere, and was adopted by IAEA and the developed nations with nuclear facilities. Over 50 years studies have been proved the technical feasibility of geological disposal for radioactive waste. However, there are many subjective and objective uncertainties on development, operation and closure of a geological disposal facility. For providing flexibility in responding to new technical information, advances in waste management and materials technologies, and in enabling social, economic and political aspects to be addressed, it is necessary to evaluate the uncertainties for all the R and D steps of a geological disposal program. (authors)

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  15. 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)

  16. Safety in the Chemical Laboratory: Contracts to Dispose of Laboratory Waste.

    Science.gov (United States)

    Fischer, Kenneth E.

    1985-01-01

    Presents a sample contract for disposing of hazardous wastes in an environmentally sound, timely manner in accordance with all federal, state, and local requirements. Addresses situations where hazardous waste must be disposed of outside the laboratory and where alternate disposal methods are not feasible. (JN)

  17. Exploiting synergies between the UK and Japanese geological disposal programmes

    International Nuclear Information System (INIS)

    Scourse, Ellie; Kawamura, Hideki; McKinley, Ian G.

    2011-01-01

    The early '80s UK programme for deep geological disposal of high-level radioactive waste was advanced and at the stage of characterising potential sites. When this project was put on hold in the mid '80s, much expertise in this field was lost. In Japan R and D in the '80s resulted in major generic safety assessments to demonstrate feasibility in the '90s. This led to the establishment of NUMO (Nuclear Waste Management Organization of Japan) and the initiation of siting based on volunteerism. This novel approach required more flexible methodology and tools for site characterisation, repository design and safety assessment. NUMO and supporting R and D organisations in Japan have invested much time and effort preparing for volunteers but, unfortunately, no discussions with potential host communities have yet developed to the point where technical work is initiated. Presently, the UK is moving forward; with the NDA RWMD (Nuclear Decommissioning Agency Radioactive Waste Management Directorate) adopting a NUMO-style volunteering approach and a flexible design catalogue. Communities have already shown interest in volunteering. The situation is thus ideal for collaboration. The paper will expand on the opportunities for the UK and Japan to benefit from an active collaboration and discuss how this can be most efficiently implemented. (author)

  18. 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)

  19. Design concept of a knowledge management system of geological disposal technology

    International Nuclear Information System (INIS)

    Osawa, Hideaki; Umeki, Hiroyuki; Makino, Hitoshi; Takase, H.; Mckinley, I.G.; Okubo, H.

    2008-01-01

    JAEA is developing a 'Knowledge Management System' for vast quantities of data or information arising from various sources relevant to the geological disposal programs in Japan. The geological disposal project is taking a stepwise approach to selecting a disposal site and, to the approval and licensing, construction, operation and closure of a repository. It is a long-term project required approximately 100 years. In this paper, in order to structuralize, as knowledge, the results of R and D on geological disposal technologies of high-level radioactive wastes, the knowledge management approach was first reviewed. The paper is followed by descriptions of the technical characteristics, procedure to carry out a plan, and education of geological disposal technologies such as knowledge management etc. The structuring of the knowledge base and the knowledge management system including the construction of safety case were described. (S. Ohno)

  20. 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

  1. Workshop on the role of natural analogs in geologic disposal of high-level nuclear waste

    International Nuclear Information System (INIS)

    Murphy, W.M.; Kovach, L.A.

    1995-01-01

    A workshop on the Role of Natural Analogs in Geologic Disposal of High-Level Nuclear Waste (HLW) was held in San Antonio, Texas, on July 22-25, 1991. It was sponsored by the US Nuclear Regulatory Commission (NRC) and the Center for Nuclear Waste Regulatory Analyses (CNWRA). Invitations to the workshop were extended to a large number of individuals with a variety of technical and professional interests related to geologic disposal of nuclear waste and natural analog studies. The objective of the workshop was to examine the role of natural analog studies in performance assessment, site characterization, and prioritization of research related to geologic disposal of HLW

  2. Environmental Impact Assessment in Geological Disposal and in Decommissioning

    International Nuclear Information System (INIS)

    O'sullivan, P.J.

    2002-01-01

    This note is based upon a report prepared under contract with the European Commission, DG-Energy and Transport, that formed the basis for discussions at the 'Club of Agencies' meeting at Oskarshamn, Sweden, on 22-24 October 2001. The author is grateful to the Commission's services for the permission to present the information also to the NEA WPDD meeting in Paris on 5 December 2001. The note discusses the results of two major studies undertaken for the European Commission (DG Environment) on the application of environmental impact assessment to the development consent process for the following projects in the nuclear field: (1) geological repositories and long-term storage facilities; (2) (and of especial relevance in the context of this meeting) the decommissioning of nuclear power plants. The first study was undertaken during 1998 and the first half of 1999 by the following consortium of companies: Nirex (UK), University of Wales Aberystwyth (UK), ENRESA (Spain), SKB (Sweden) and ONDRAF/NIRAS (Belgium). The second study was undertaken during 2000 and the first quarter of 2001, by the European Economic Interest Grouping Cassiopee, together with the University of Wales Aberystwyth, ECA Global (Spain). Both studies were managed by Nirex. (author)

  3. 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

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

    International Nuclear Information System (INIS)

    Zheng Hualing; Chen Shi; Sun Donghui

    2007-01-01

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

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

    International Nuclear Information System (INIS)

    Hiruzawa, Shigenobu

    2004-01-01

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

  6. Advances in Geologic Disposal System Modeling and Application to Crystalline Rock

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-22

    The Used Fuel Disposition Campaign (UFDC) of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (OFCT) is conducting research and development (R&D) on geologic disposal of used nuclear fuel (UNF) and high-level nuclear waste (HLW). Two of the high priorities for UFDC disposal R&D are design concept development and disposal system modeling (DOE 2011). These priorities are directly addressed in the UFDC Generic Disposal Systems Analysis (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media (e.g., salt, granite, clay, and deep borehole disposal). This report describes specific GDSA activities in fiscal year 2016 (FY 2016) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code and the Dakota uncertainty sampling and propagation code. Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through engineered barriers and natural geologic barriers to the biosphere. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

  7. 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

  8. Building technical and social confidence in the safety of geological disposal in Japan

    International Nuclear Information System (INIS)

    Tochiyama, Osamu; Masuda, Sumio

    2013-01-01

    Geological disposal has been adopted as the most feasible option for the method of long-term management of high-level radioactive waste (HLW) in every country in the world, regardless of the pros and cons of the nuclear power generation. Building stakeholders’ confidence in safety of geological disposal is indispensable to reach the point where the implementation of geological disposal is accepted by the current generation. The safety case is a key input to build confidence in geological disposal stepwise as the program progresses and regarded to play an important role as a common platform in the communication among stakeholders. The aim of this paper is to review arguments relevant to building technical and social confidence in the progress of Japanese research and development activities as well as international discussions. (author)

  9. Study on the background information for the R and D of geological disposal

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Hirusawa, Shigenobu; Komoto, Harumi

    2001-02-01

    It is quite important for Japan Nuclear Cycle Development Institute (JNC) to analyze the R and D items after 'H12 report' and also provide their results of R and D activities to general public effectively. Recognizing the importance of the social consensus to the geological disposal, relating background informations were to be picked up. In this fiscal year, following two main topics were selected and studied. 1. Research and analysis on the options for the geological disposal concept. The major nuclear power-generating countries have almost all chosen deep geological disposal as preferred method for HLW disposal. Since 1990's, to make the geological disposal flexible, the alternative concepts for the disposal of HLW have been discussed promoting the social acceptance. In this context, recent optional discussions and international evaluations on the following topics were studied and summarized. (1) Reversibility of waste disposal/Retrievability of waste/Waste monitoring, (2) Long-term storage concept and its effectiveness, (3) Present position and role of international disposal. 2. Research and analysis on some educational materials collected from foreign countries. Although geological disposals is scheduled to start still in future, it is quite important to study the procedures to attract younger generation and get their proper perceptions on the nuclear energy and waste problems. As the supporting analysis to implement strategically the public relational activities for JNC's geological disposal R and D, particular attention was focused on the educational materials obtained in the last year's survey. Representative educational materials were selected and following items were studied and summarized. (1) Basic approach, positioning and characteristics of the educational materials, (2) Detailed analysis of the representatively selected educational materials, (3) Comparison of the analyzed characteristics and study on its feedback to Japanese materials. (author)

  10. Geological Disposal of Radioactive Waste: A Long-Term Socio-Technical Experiment.

    Science.gov (United States)

    Schröder, Jantine

    2016-06-01

    In this article we investigate whether long-term radioactive waste management by means of geological disposal can be understood as a social experiment. Geological disposal is a rather particular technology in the way it deals with the analytical and ethical complexities implied by the idea of technological innovation as social experimentation, because it is presented as a technology that ultimately functions without human involvement. We argue that, even when the long term function of the 'social' is foreseen to be restricted to safeguarding the functioning of the 'technical', geological disposal is still a social experiment. In order to better understand this argument and explore how it could be addressed, we elaborate the idea of social experimentation with the notion of co-production and the analytical tools of delegation, prescription and network as developed by actor-network theory. In doing so we emphasize that geological disposal inherently involves relations between surface and subsurface, between humans and nonhumans, between the social, material and natural realm, and that these relations require recognition and further elaboration. In other words, we argue that geological disposal concurrently is a social and a technical experiment, or better, a long-term socio-technical experiment. We end with proposing the idea of 'actor-networking' as a sensitizing concept for future research into what geological disposal as a socio-technical experiment could look like.

  11. 2005 dossier: clay. Tome: architecture and management of the geologic disposal facility

    International Nuclear Information System (INIS)

    2005-01-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the design of a geologic disposal facility for high-level and long-lived radioactive wastes in argilite formations. Content: 1 - approach of the study: goal, main steps of the design study, iterative approach, content; 2 - general description: high-level and long-lived radioactive wastes, purposes of a reversible disposal, geologic context of the Meuse/Haute-Marne site - the Callovo-Oxfordian formation, design principles of the disposal facility architecture, role of the different disposal components; 3 - high-level and long-lived wastes: production scenarios, description of primary containers, inventory model, hypotheses about receipt fluxes of primary containers; 4- disposal containers: B-type waste containers, C-type waste containers, spent fuel disposal containers; 5 - disposal modules: B-type waste disposal modules, C-type waste disposal modules, spent-fuel disposal modules; 6 - overall underground architecture: main safety questions, overall design, dimensioning factors, construction logic and overall exploitation of the facility, dimensioning of galleries, underground architecture adaptation to different scenarios; 7 - boreholes and galleries: general needs, design principles retained, boreholes description, galleries description, building up of boreholes and galleries, durability of facilities, backfilling and sealing up of boreholes and galleries; 8 - surface facilities: general organization, nuclear area, industrial and administrative area, tailings area; 9 - nuclear exploitation means of the facility: receipt of primary containers and preparation of disposal containers, transfer of disposal containers from the surface to the disposal alveoles, setting up of containers inside alveoles; 10 - reversible management of the disposal: step by step disposal process, mastery of disposal behaviour and action capacity, observation and

  12. Final disposal in deep boreholes using multiple geological barriers. Digging deeper for safety. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Bracke, Guido; Hurst, Stephanie; Merkel, Broder; Mueller, Birgit; Schilling, Frank

    2016-03-15

    The proceedings of the workshop on final disposal in deep boreholes using multiple geological barriers - digging deeper for safety include contributions on the following topics: international status and safety requirements; geological and physical barriers; deep drilling - shaft building; technical barriers and emplacement technology for high P/T conditions; recovery (waste retrieval); geochemistry and monitoring.

  13. 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.

  14. Office of Geologic Respositories issues hierarchy for a Mined Geologic Disposal System (OGR/B-10)

    International Nuclear Information System (INIS)

    1986-09-01

    The Office of Geologic Repositories (OGR) has adopted an issues hierarchy for use by all Project Offices. The issues hierarchy provides a framework for representing issues related to regulatory requirements for siting and licensing a mined geologic disposal system (MGDS) and for describing the work that needs to be completed during site characterization to resolve those issues. The issues in the issues hierarchy are defined as the questions relating to the performance of the MGDS that must be resolved to demonstrate compliance with the applicable federal regulations (including 10 CFR Part 60, 10 CFR Part 960, 40 CFR Part 191, and 10 CFR Part 20). The issues hierarchy is structured around four broad areas of regulatory concern related to the requirements for siting and licensing an MGDS (postclosure performance, preclosure radiological safety, non-radiological environmental impacts, and feasibility and cost of MGDS development), and provides the framework for definition of the information needed to satisfy the applicable regulatory requirements in each of these areas. The purpose of this document is to present the issues hierarchy, describe the rationale used to develop the hierarchy, and describe how the issues hierarchy is used in program planning. Section 2 presents the overall rationale for the issues hierarchy, and explains the structure and organization of the hierarchy. Section 3 presents the issues hierarchy itself and Section 4 describes the basis for the development of individual issues. Section 5 provides a correlation between the issues and the applicable federal regulations being addressed. Section 6 describes how the issues drive development of plans in support of siting and licensing requirements through use of an issue resolution strategy that includes performance allocation

  15. 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)

  16. Experience in selection and characterization of sites for geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    1997-12-01

    An important matter in the development of a geological repository for disposal radioactive waste is the selection of a site that has characteristics that are favorable for isolation. A number of Member States have had national programmes under way for several decades to investigate sites to gather the geological information needed to design and construct a safe repository. The purpose of this report is to document this experience and to summarize what has been learned about the site selection and investigation process. It is hoped it will be of interest to scientists and engineers working in national disposal programmes by providing them information and key references regarding the disposal programmes in other countries. It may also be of interest to members of the public and to decision makers wanting an overview of the worldwide status of programmes to select and characterize geological disposal sites for radioactive waste

  17. Synopsis of in situ testing for mined geologic disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Gnirk, P.F.

    1980-01-01

    The concept of mined geologic disposal of radioactive wastes was proposed about 25 years ago. Until the mid-1970's, research and development activities were directed essentially to the evaluation of the disposal concept fot salt formations. During the past 5 years, the waste disposal technology programs in the USA and other countries have been expanded substantially in effort and scope for evaluation of a broader range of geologic media beyond salt, including basalt, granite, shale, and tuff. From the outset, in situ testing has been an integral part of these programs, and has included activities concerned with rock mass characterization, the phenomenological response of rock to waste or simulated waste emplacement, model development and verification, and repository design. This paper provides a synopsis of in situ tests that have been or are being performed in geologic media in support of the waste disposal programs in the USA, the United Kingdom, Sweden, and the Federal Republic of Germany

  18. Researches on tectonic uplift and denudation with relation to geological disposal of HLW in Japan

    International Nuclear Information System (INIS)

    Fujiwara, Osamu; Sanga, Tomoji; Moriya, Toshifumi

    2005-01-01

    This paper reviews the present state of researches on tectonic uplift and denudation, and shows perspective goals and direction of future researches from the viewpoint of geological disposal of HLW in Japan. Detailed history of tectonics and denudation in geologic time scale, including the rates, temporal and spatial distributions and processes, reconstructed from geologic and geomorphologic evidences will enable us to make the geological predictions. Improvements of the analytic methods for the geological histories, e.g. identification of the tectonic and denudational imprints and age determinations, are indispensable for the accurate prediction. Developments of the tools and methodologies for assessments of the degree and extension of influences by the tectonic uplift, subsidence and denudation on the geological environments such as ground water flows are also fundamental problem in the study field of the geological disposal of HLW. Collaboration of scientific researches using the geological and geomorphological methods and applied technology, such as numerical simulations of ground water flows, is important in improving the safety and accuracy of the geological disposal of HLW. (author)

  19. 2005 dossier: granite. Tome: phenomenological evolution of the geologic disposal; Dossier 2005: Granite. Tome evolution phenomenologique du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

  20. Key scientific challenges in geological disposal of high level radioactive waste

    International Nuclear Information System (INIS)

    Wang Ju

    2007-01-01

    The geological disposal of high radioactive waste is a challenging task facing the scientific and technical world. This paper introduces the latest progress of high level radioactive disposal programs in the latest progress of high level radioactive disposal programs in the world, and discusses the following key scientific challenges: (1) precise prediction of the evolution of a repository site; (2) characteristics of deep geological environment; (3) behaviour of deep rock mass, groundwater and engineering material under coupled con-ditions (intermediate to high temperature, geostress, hydraulic, chemical, biological and radiation process, etc); (4) geo-chemical behaviour of transuranic radionuclides with low concentration and its migration with groundwater; and (5) safety assessment of disposal system. Several large-scale research projects and several hot topics related with high-level waste disposal are also introduced. (authors)

  1. 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.)

  2. Rock solid: the geology of nuclear waste disposal

    International Nuclear Information System (INIS)

    Reid, Elspeth.

    1990-01-01

    With a number of nuclear submarines and power stations due to be decommissioned in the next decade, stores of radioactive waste, and arguments about storage increase. Whatever the direction taken by the nuclear industry in Britain, the legacy of waste remains for the foreseeable future. Geology is at the heart of the safety argument for nuclear wastes. It is claimed that rocks should act as the main safety barrier, protecting present and future generations from radiation. Rock Solid presents a clear, accessible and up to date account of the geological problems involved in building a nuclear waste repository. The author describes the geology of some of the possible UK repository sites (Sellafield, Dounreay, Altnabreac, Billingham), explains how sites are investigated (including computer models), and finally considers the crucial question: 'would geological containment of radioactive waste actually work?'. (author)

  3. 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.

  4. 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.

  5. The role of geology in the evaluation of waste disposal sites

    International Nuclear Information System (INIS)

    Ogunsanwo, O.; Mands, E.

    1999-01-01

    The construction of waste disposal sites demonstrates the awareness of the need to protect the environment against pollution. The site are constructed on foundations of soils and rocks. Photo geological studies, geophysical investigations and geological field mapping are indispensable in the selection of suitable sites. Most of the construction materials (in the case of landfills) are of geologic origin and their suitability can only be ascertained after some geological assessments. Furthermore, the hydrogeological conditions within the adjoining terrains and the flow of leachates from and within the wastes must be monitored so as to prevent pollution (radiation, in the case of radioactive wastes, can be monitored with the aid of geochemistry). Several models/systems are available for the hydrogeological/geochemical evaluation of waste disposal sites. The selection of the site and the construction materials as well as the hydrogeological/ /geochemical studies are very critical as the performance of the disposal site depends solely on these aspects. These aspects are basically within the realms of geology. It is thus obvious that geology plays a leading role in the evaluation of waste disposal sites right from the site selection stage until the site is done with

  6. 26 CFR 1.631-2 - Gain or loss upon the disposal of timber under cutting contract.

    Science.gov (United States)

    2010-04-01

    ... cutting contract. 1.631-2 Section 1.631-2 Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE... loss upon the disposal of timber under cutting contract. (a) In general. (1) If an owner disposes of... deemed to be the date such timber is cut. However, if payment is made to the owner under the contract for...

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-11-15

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

  9. 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)

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  11. 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.

  12. 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)

  13. Current status and future plans of R and D on geological disposal of HLW in Japan

    International Nuclear Information System (INIS)

    Sasaki, Noriaki

    1994-01-01

    As to the final disposal of HLW, it is considered highly important to provide a clear distinction between implementation of disposal and the research and development as independent processes, and to increase the transparency of the overall disposal program by defining concrete schedules and the roles and responsibilities of the organizations involved. The Power Reactor and Nuclear Fuel Development Corporation (PNC) has being conducted research and development on the geological disposal of HLW, as the leading organization. The responsibility of PNC is to ensure smooth progress of research and development project and to carry out studies of geological environment. The role of the Japanese government is to take overall responsibilities for appropriate and steady implementations of the program, as well as enacting any laws or policies required. On the other hand, electricity supply utilities are responsible to secure necessary funds for disposal, and in accordance with their role as waste producers, they are expected to cooperate even at the stage of research and development. Fundamental features of research and development of PNC carried out at this stage are as follows; (1) Generic research and development, (2) To establish scientific and technical bases of geological isolation of HLW in Japan, (3) About 15 years program from 1989 with documentation of progress reports, (4) Approach from near-field to far-field. PNC summarized the findings obtained by 1991, and submitted a document (H3 Report) in September 1992 as the first progress report. H3 Report is the first and comprehensive technical report on geological disposal of HLW in Japan, and provides information for the public to find out the current status of the research and development. This paper reviews the conclusions of H3 Report, overall procedures and schedule for implementing geological disposal, and future plans of R and D in PNC. (J.P.N.)

  14. 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

  15. Confinement and migration of radionuclides in deep geological disposal

    International Nuclear Information System (INIS)

    Poinssot, Ch.

    2007-07-01

    Disposing high level nuclear waste in deep disposal repository requires to understand and to model the evolution of the different repository components as well as radionuclides migration on time-frame which are well beyond the time accessible to experiments. In particular, robust and predictive models are a key element to assess the long term safety and their reliability must rely on a accurate description of the actual processes. Within this framework, this report synthesizes the work performed by Ch. Poinssot and has been prepared for the defense of his HDR (French university degree to Manage Research). These works are focused on two main areas which are (i) the long term evolution of spent nuclear fuel and the development of radionuclide source terms models, and (ii) the migration of radionuclides in natural environment. (author)

  16. Study on risk communication support system of geological disposal

    International Nuclear Information System (INIS)

    Higuchi, Natsuko; Yoshizawa, Yuji; Takeuchi, Mitsuo; Kitayama, Kazumi; Kobayashi, Yoko

    2008-01-01

    In order to smoothly implement the selection of a final site for disposal of high-level radioactive waste (HLW), it is necessary to ensure effective communication with various stakeholders and to gain public confidence. Text mining technology can extract useful information from texts such as symposium dialogs or questionnaires after a lecture. The problem and its solution are extracted by structuring and visualizing the topics and it is possible to obtain feedback information for the next symposium or lecture and/or posterity. We applied text mining to analyze a facilitation of panel discussion and to understand future researchers. The development of such an analysis technique will contribute to mutual confidence and agreement among all the stakeholders in a HLW disposal project. (author)

  17. Cost and ways of financing of the geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Venet, P.; Baetsle, L.H.; Barthoux, A.; Engelmann, H.J.

    1986-01-01

    In the paper, the costs of geological disposal of radioactive waste are initially evaluated for a certain number of representative cases of present tendencies in the European Community. These expenses comprise research, development and site validation costs, transport and interim storage costs and finally expenditure relating to various investment and exploitation phases of the disposal site as well as its closure. The possible ways of financing are subsequently reviewed and the financial charges which resulted are calculated for each considered scenario. (author)

  18. Geologic disposal of nuclear wastes: salt's lead is challenged

    International Nuclear Information System (INIS)

    Kerr, R.A.

    1979-01-01

    The types of radioactive waste disposal sites available are outlined. The use of salt deposits and their advantages are discussed. The reasons for the selection of the present site for the Waste Isolation Pilot Plant are presented. The possibilities of using salt domes along the Gulf Coast and not-salt rocks as nuclear waste repositories are also discussed. The sea bed characteristics are described and advantages of this type of site selection are presented

  19. 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.)

  20. Time evolution of the Clay Barrier Chemistry in a HLW deep geological disposal in granite

    International Nuclear Information System (INIS)

    Font, I.; Miguel, M. J.; Juncosa, R.

    2000-01-01

    The main goal of a high level waste geological disposal is to guarantee the waste isolation from the biosphere, locking them away into very deep geological formations. The best way to assure the isolation is by means of a multiple barrier system. These barriers, in a serial disposition, should assure the confinement function of the disposal system. Two kinds of barriers are considered: natural barriers (geological formations) and engineered barriers (waste form, container and backfilling and sealing materials). Bentonite is selected as backfilling and sealing materials for HLW disposal into granite formations, due to its very low permeability and its ability to fill the remaining spaces. bentonite has also other interesting properties, such as, the radionuclide retention capacity by sorption processes. Once the clay barrier has been placed, the saturation process starts. The granite groundwater fills up the voids of the bentonite and because of the chemical interactions, the groundwater chemical composition varies. Near field processes, such as canister corrosion, waste leaching and radionuclide release, strongly depends on the water chemical composition. Bentonite pore water composition is such a very important feature of the disposal system and its determination and its evolution have great relevance in the HLW deep geological disposal performance assessment. The process used for the determination of the clay barrier pore water chemistry temporal evolution, and its influence on the performance assessment, are presented in this paper. (Author)

  1. The study of the national context in support of planning geological disposal in Romania - 15232

    International Nuclear Information System (INIS)

    Andrei, V.; Prisecary, I.

    2015-01-01

    In this paper a risk management process was studied to assess the Romanian national context concerning the setting of a geological disposal of radioactive waste. A PESTEL analysis involving political, economical, social, technical, environmental and legal issues, has been performed to identify factors that could endanger the project. The analysis of a pessimistic scenario indicates the national context could delay the schedule of the siting and site licensing process by 17.5 years. The estimation of a maximum time of 38 years for this process was considered realistic since this value was met in the countries which were confronted with suspensions/reconsiderations of the siting process of a geological disposal facility

  2. 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

  3. 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

  4. Study on advanced systematic function of the JNC geological disposal technical information integration system. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito Takaya

    2004-02-01

    In this study, while attaining systematization about the technical know-how mutually utilized between geology environmental field, disposal technology (design) field and safety assessment field, the share function of general information in which the formation of an information share and the use promotion between the technical information management databases built for every field were aimed at as an advancement of the function of JNC Geological Disposal Technical Information Integration System considered, and the system function for realizing considered in integration of technical information. (1) Since the concrete information about geology environment which is gradually updated with progress of stratum disposal research, or increases in reflected suitable for research of design and safety assessment. After arranging the form suitable for systematizing technical information, while arranging the technical information in both the fields of design and safety assessment with the form of two classes based on tasks/works, it systematized planning adjustment about delivery of technical information with geology environmental field. (2) In order to aim at integration of 3-fields technical information of geological disposal, based on the examination result of systematization of technical information, the function of mutual use of the information managed in two or more databases was considered. Moreover, while considering system functions, such as management of the use history of technical information, connection of information use, and a notice of common information, the system operation windows in consideration of the ease of operation was examined. (author)

  5. 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

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

    International Nuclear Information System (INIS)

    Savage, D.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

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

    1980-05-01

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

  8. Three-dimensional Geological and Geo-mechanical Modelling of Repositories for Nuclear Waste Disposal in Deep Geological Structures

    International Nuclear Information System (INIS)

    Fahland, Sandra; Hofmann, Michael; Bornemann, Otto; Heusermann, Stefan

    2008-01-01

    To prove the suitability and safety of underground structures for the disposal of radioactive waste extensive geo-scientific research and development has been carried out by BGR over the last decades. Basic steps of the safety analysis are the geological modelling of the entire structure including the host rock, the overburden and the repository geometry as well as the geo-mechanical modelling taking into account the 3-D modelling of the underground structure. The geological models are generated using the special-construction openGEO TM code to improve the visualisation an d interpretation of the geological data basis, e.g. borehole, mine, and geophysical data. For the geo-mechanical analysis the new JIFE finite-element code has been used to consider large 3-D structures with complex inelastic material behaviour. To establish the finite-element models needed for stability and integrity calculations, the geological models are simplified with respect to homogenous rock layers with uniform material behaviour. The modelling results are basic values for the evaluation of the stability of the repository mine and the long-term integrity of the geological barrier. As an example of application, the results of geological and geo-mechanical investigations of the Morsleben repository based on 3-D modelling are presented. (authors)

  9. Numerical investigation of high level nuclear waste disposal in deep anisotropic geologic repositories

    KAUST Repository

    Salama, Amgad; El Amin, Mohamed F.; Sun, Shuyu

    2015-01-01

    One of the techniques that have been proposed to dispose high level nuclear waste (HLW) has been to bury them in deep geologic formations, which offer relatively enough space to accommodate the large volume of HLW accumulated over the years since

  10. 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)

  11. Monitoring of waste disposal in deep geological formations

    Science.gov (United States)

    German, V.; Mansurov, V.

    2003-04-01

    In the paper application of kinetic approach for description of rock failure process and waste disposal microseismic monitoring is advanced. On base of two-stage model of failure process the capability of rock fracture is proved. The requests to monitoring system such as real time mode of data registration and processing and its precision range are formulated. The method of failure nuclei delineation in a rock masses is presented. This method is implemented in a software program for strong seismic events forecasting. It is based on direct use of the fracture concentration criterion. The method is applied to the database of microseismic events of the North Ural Bauxite Mine. The results of this application, such as: efficiency, stability, possibility of forecasting rockburst are discussed.

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  13. 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

  14. 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.)

  15. Study to optimize a disposal tunnel layout taking into account heterogeneous characteristics of the geological environment

    International Nuclear Information System (INIS)

    Suyama, Yasuhiro; Toida, Masaru; Yanagizawa, Koichi

    2007-01-01

    The geological environment has spatially heterogeneous characteristics with varied host rock types, fractures and so on. In this case the generic disposal tunnel layout, which has been designed by JNC, is not the most suitable for HLW disposal in Japan. The existence of spatially heterogeneous characteristics means that in the repository region there exist sub-regions that are more favorable from the perspective of long-term safety and ones that are less favorable. In order that the spatially heterogeneous environment itself may be utilized most effectively as an NBS, an alternative design of disposal tunnel layout is required. Focusing on the geological environment with spatially heterogeneous characteristics, the authors have developed an alternative design of disposal tunnel layout. The alternative design adopts an optimization approach using a 'variable disposal tunnel layout'. The optimization approach minimizes the number of locations where major water conducting fractures are intersected, and maximizes the number of emplacement locations for waste packages. This paper will outline the variable disposal tunnel layout and its applicability. (author)

  16. Safety and sensitivity analyses of a generic geologic disposal system for high-level radioactive waste

    International Nuclear Information System (INIS)

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

    1994-11-01

    This report describes safety and sensitivity analyses of a generic geologic disposal system for HLW, using a GSRW code and an automated sensitivity analysis methodology based on the Differential Algebra. An exposure scenario considered here is based on a normal evolution scenario which excludes events attributable to probabilistic alterations in the environment. The results of sensitivity analyses indicate that parameters related to a homogeneous rock surrounding a disposal facility have higher sensitivities to the output analyzed here than those of a fractured zone and engineered barriers. The sensitivity analysis methodology provides technical information which might be bases for the optimization of design of the disposal facility. Safety analyses were performed on the reference disposal system which involve HLW in amounts corresponding to 16,000 MTU of spent fuels. The individual dose equivalent due to the exposure pathway ingesting drinking water was calculated using both the conservative and realistic values of geochemical parameters. In both cases, the committed dose equivalent evaluated here is the order of 10 -7 Sv, and thus geologic disposal of HLW may be feasible if the disposal conditions assumed here remain unchanged throughout the periods assessed here. (author)

  17. International Approaches for Nuclear Waste Disposal in Geological Formations: Report on 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); Persoff, Peter [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)

    2016-09-01

    The goal of the Fifth Worldwide Review is to document evolution in the state-of-the-art of approaches for nuclear waste disposal in geological formations since the Fourth Worldwide Review that was released in 2006. The last ten years since the previous Worldwide Review has seen major developments in a number of nations throughout the world pursuing geological disposal programs, both in preparing and reviewing safety cases for the operational and long-term safety of proposed and operating repositories. The countries that are approaching implementation of geological disposal will increasingly focus on the feasibility of safely constructing and operating their repositories in short- and long terms on the basis existing regulations. The WWR-5 will also address a number of specific technical issues in safety case development along with the interplay among stakeholder concerns, technical feasibility, engineering design issues, and operational and post-closure safety. Preparation and publication of the Fifth Worldwide Review on nuclear waste disposal facilitates assessing the lessons learned and developing future cooperation between the countries. The Report provides scientific and technical experiences on preparing for and developing scientific and technical bases for nuclear waste disposal in deep geologic repositories in terms of requirements, societal expectations and the adequacy of cases for long-term repository safety. The Chapters include potential issues that may arise as repository programs mature, and identify techniques that demonstrate the safety cases and aid in promoting and gaining societal confidence. The report will also be used to exchange experience with other fields of industry and technology, in which concepts similar to the design and safety cases are applied, as well to facilitate the public perception and understanding of the safety of the disposal approaches relative to risks that may increase over long times frames in the absence of a successful

  18. IRSN safety research carried out for reviewing geological disposal safety case

    International Nuclear Information System (INIS)

    Serres, Christophe; Besnus, Francois; Gay, Didier

    2010-01-01

    The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

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

    International Nuclear Information System (INIS)

    Skopovy, J.; Woller, F.

    1997-01-01

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

  20. Visualized materials of information on HLW geological disposal for promotion of public understanding

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Yoshikawa, Hideki; Kashiwazaki, Hiroshi

    2003-03-01

    Japan Nuclear Cycle Development Institute (JNC) has a few thousands of short term visitors to Geological Isolation Basic Research Facility of Tokai works in every year. From the viewpoint of promotion of the visitor's understanding and also smooth communication between researchers and visitors, the explanation of the technical information on geological disposal should be carried out in more easily understandable methods, as well as conventional tour to the engineering-scale test facility (ENTRY). The images of repository operation, output data of technical calculations regarding geological disposal were visualized. We can use them practically as one of the useful explanation tools to support visitor's understanding. The visualized materials are attached to this report with the DVD-R media, furthermore, background information of each visualized materials was documented. (author)

  1. [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

  2. Qualitative acceptance criteria for radioactive wastes to be disposed of in deep geological formations

    International Nuclear Information System (INIS)

    1990-05-01

    The present Safety Guide has to be seen as a companion document to the IAEA Safety Series No. 99. It is concerned with the waste form which is an important component of the overall disposal system. Because of the broad range of waste types and conditioned forms and variations in the sites, designs and constructional approaches being considered for deep geological repositories, this report necessarily approaches the waste acceptance criteria in a general way, recognizing that the assignment of quantitative limits to these criteria has to be the responsibility of national authorities. The main objective of this Safety Guide is to set out qualitative waste acceptance criteria as a basis for specifying quantitative limits for the waste forms and packages which are intended to be disposed of in deep geological repositories. It should serve as guidance for assigning such parameter values which would fully comply with the safety assessment and performance of a waste disposal system as a whole. This document is intended to serve both national authorities and regulatory bodies involved in the development of deep underground disposal systems. The qualitative waste acceptance criteria dealt with in the present Safety Guide are primarily concerned with the disposal of high level, intermediate level and long-lived alpha bearing wastes in deep geological repositories. Although some criteria are also applicable in other waste disposal concepts, it has to be borne in mind that the set of criteria presented here shall ensure the isolation capability of a waste disposal system for periods of time much longer than for other waste streams with shorter lifetimes. 51 refs, 1 tab

  3. Present situation and perspective of China's geological disposal of high-level radioactive waste

    International Nuclear Information System (INIS)

    Zhang, H.

    2005-01-01

    The theme of the conference, 'Political and Technical Progress of Geologic Repositories', has drawn world-wide attention and remains a challenging topic facing the nuclear industry. I am delighted to attend this important conference and have the opportunity to state our views. And I would like to express my gratitude to our host Sweden and IAEA. The development of nuclear science and technology and the peaceful uses of nuclear energy is one of the greatest achievements of the mankind in the 20. century. The development and progress of nuclear technology, from application of fission energy to the exploration of fusion energy, embodies the mankind's expectation to the future. It will be the major energy of final settlement of the issue of global sustainable development. The safe and effective treatment and disposal of nuclear waste are of vital importance to the peaceful uses of nuclear energy and technology. The most dangerous and long-lived waste has to be contained and isolated from the human living environment. Construction of geologic repository in appropriate geological formation for radioactive waste disposal is being accepted as a suitable solution and being studied widely. In the International Conference on Geological Repositories held in Denver, U.S.A., in November 1999, senior governmental representatives from more than 20 countries stated related policies and decisions of their respective countries, which caught world-wide attention. I am convinced that this conference, an event about geologic repository following the Denver conference, will produce positive results for the safe and effective disposal of nuclear waste. Now I would like to take this opportunity to brief you on China's current situation and perspectives of geologic disposal of high-level radioactive waste. (author)

  4. Cement-based grouts in geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Onofrei, M.

    1996-01-01

    The behavior and performance of a specially developed high-performance cement-based grout has been studied through a combined laboratory and in situ research program conducted under the auspices of the Canadian Nuclear Fuel Waste Management Program (CNFWMP). A new class of cement-based grouts - high-performance grouts-with the ability to penetrate and seal fine fractures was developed and investigated. These high-performance grouts, which were injected into fractures in the granitic rock at the Underground Research Laboratory (URL) in Canada, are shown to successfully reduce the hydraulic conductivity of the rock mass from -7 m s -1 to 10 -9 m s -1 and to penetrate fissures in the rock with apertures as small as 10 μm. Furthermore, the laboratory studies have shown that this high - performance grout has very low hydraulic conductivity and is highly leach resistant under repository conditions. Microcracks generated in this materials from shrinkage, overstressing or thermal loads are likely to self-seal. The results of these studies suggest that the high-performance grouts can be considered as viable materials in disposal-vault sealing applications. Further work is needed to fully justify extrapolation of the results of the laboratory studies to time scales relevant to performance assessment

  5. Swedish programme for disposal of radioactive waste - geological aspects

    International Nuclear Information System (INIS)

    Baeckblom, G.; Karlsson, Fred

    1990-01-01

    Spent nuclear fuel and radioactive wastes of different types are generated in the course of electrical production. These wastes, which already exist and will continue to exist irrespective of the future for nuclear power in Sweden, are potential hazards if not properly managed. SKB in close co-operation with Swedish and international scientists and engineers have demonstrated the need to construct and operate a waste management system that will ensure very high safety for a long period of time. SKB has further demonstrated that with presently available technology it is possible to construct a final repository for long-lived wastes in Sweden that meets very high standards with respect to safety and radiation protection. SKB has also presented a programme for the research, development and other measures that are required to achieve an optimized disposal site system in Sweden. This programme is comprehensive and the strong support of national and international experts. Examples of research projects discussed in the present paper are: (a) efforts to describe the major zones in the rock mass, (b) characterization of low-conductive rock masses, (c) studies of post-glacial faulting and (d) the importance of natural analogues. The rationale for one of the most important projects in progress - the Hard Rock Laboratory - is also presented. (authors)

  6. Safety of geological disposal of high-level waste

    International Nuclear Information System (INIS)

    Ohe, Toshiaki; Tsukamoto, Masaki

    1989-01-01

    This paper represents an analysis of barrier performance of high-level waste disposal. Advantages of a multi-barrier system in repository are checked through experiments and simulations; thermal restriction, glass-leaching, and nuclide migration in both buffer materials and surrounding rock media. The temperature distribution in a repository is calculated with TRUMP code, then the pit interval is determined according to the temperature criteria of compacted bentonite. The simulation code for glass corrosion, STRAG, is developed on the basis of the experimental findings of the JSS project in which the actual radioactive glass fabricated CEA/Marcoule was used. STRAG is then verified through agreements of the simulated and measured values. Nuclide migration in compacted bentonite is calculated by SWIFT code, and the results show the bentonite capability for retention of nuclides released from waste glass. Migration of cesium isotope in rock is also examined with the small granite core samples, of which results suggest that bulk-granite except for fractures is expected as a porous media. (author)

  7. Geologic disposal as optimal solution of managing the spent nuclear fuel and high-level radioactive waste

    International Nuclear Information System (INIS)

    Ilie, P.; Didita, L.; Ionescu, A.; Deaconu, V.

    2002-01-01

    To date there exist three alternatives for the concept of geological disposal: 1. storing the high-level waste (HLW) and spent nuclear fuel (SNF) on ground repositories; 2. solutions implying advanced separation processes including partitioning and transmutation (P and T) and eventual disposal in outer space; 3. geological disposal in repositories excavated in rocks. Ground storing seems to be advantageous as it ensures a secure sustainable storing system over many centuries (about 300 years). On the other hand ground storing would be only a postponement in decision making and will be eventually followed by geological disposal. Research in the P and T field is expected to entail a significant reduction of the amount of long-lived radioactive waste although the long term geological disposal will be not eliminated. Having in view the high cost, as well as the diversity of conditions in the countries owning power reactors it appears as a reasonable regional solution of HLW disposal that of sharing a common geological disposal. In Romania legislation concerning of radioactive waste is based on the Law concerning Spent Nuclear Fuel and Radioactive Waste Management in View of Final Disposal. One admits at present that for Romania geological disposal is not yet a stressing issue and hence intermediate ground storing of SNF will allow time for finding a better final solution

  8. 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)

  9. 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.

  10. 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)

  11. 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.

  12. 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)

  13. Development of an integrated software system (Digital Geological Disposal System) for design and evaluation of HLW disposal system

    International Nuclear Information System (INIS)

    Fusaeda, Shigeki; Yanagisawa, Ichiro; Imamura, Naoko

    2000-02-01

    In this study, a design study on 'Digital Geological Disposal System' has been carried out in order to define the developmental goal for the first phase (- FY2002) system and to demonstrate the feasibility of the system development. The key conclusions are summarized as follows: (1) As the result of the basic design of the Integrated Analysis Platform (IAP), the representation method for PLAN (Process Linkage Analysis Network), the PLAN objects configuration and definition and the execution control mechanism of PLAN are newly proposed in order to enhance the flexibility of IAP. (2) A prototyping study concerning an optimization problem that includes cavity stability analysis and thermal analysis, showed that the design of IAP is practical one and also has enough flexibility to solve complex problems expected in the repository design processes. (3) The development plan for the Digital Geological Disposal System' has been investigated based on the discussions about the system usage by the potential users such as the regulators, the implementation body and the research institutes, as well as the technical discussions. As a result, short-term (for the first phase) and long-term development plans have been proposed. (author)

  14. Development of an integrated software system (Digital Geological Disposal System) for design and evaluation of HLW disposal system

    International Nuclear Information System (INIS)

    Fusaeda, Shigeki; Yanagisawa, Ichiro; Imamura, Naoko

    2000-02-01

    In this study, a design study on 'Digital Geological Disposal System' has been carried out in order to define the developmental goal for the first phase (-FY2002) system and to demonstrate the feasibility of the system development. The key conclusions are summarized as follows: (1) As the result of the basic design of the Integrated Analysis Platform (IAP), the representation method for the procedure of analysis that is called analysis network, the configuration of the object that makes up the analysis network, and the execution control mechanism of the analysis network are newly proposed in order to enhance the flexibility of IAP. (2) A prototyping study concerning an optimization problem that includes cavity stability analysis and thermal analysis, showed that the design of IAP is practical one and also has enough flexibility to solve complex problems expected in the repository design processes. (3) The development plan for the 'Digital Geological Disposal System' has been investigated based on the discussions about the system usage by the potential users such as the regulators, the implementation body and the research institutes, as well as the technical discussions. As a result, short-term (for the first phase) and long-term development plans have been proposed. (author)

  15. 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

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

    Science.gov (United States)

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

    2016-11-15

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

  17. Current safety issues in the development of geological disposal of radioactive waste in France

    International Nuclear Information System (INIS)

    Raimbault, P.

    2002-01-01

    Deep geological disposal of high level and medium level long-lived waste in France is one of the three research paths defined by the law of 30th December 1991 on radioactive waste management. Research should be undertaken on: separation and transmutation of long-lived radionuclides in these waste; reversible or non reversible disposal in deep geological layers supported by investigations in underground laboratories; processes for conditioning and long term surface storage of these waste. In 2006, a global evaluation report on this research should be established by the Government and sent to the French Parliament. On this basis the Parliament should promulgate a law providing new objectives for the research and possibly presenting a framework for a deep disposal process. The French Nuclear Safety Authority has the responsibility to license the underground laboratories foreseen in the second research path and the nuclear facilities involved in the first and third research paths and make sure that existing high level and medium level long-lived waste currently produced are properly managed. It will give its advice on the safety aspects associated to the envisaged future management options. Its main concern is that results obtained in 2006 will be conclusive enough to take decisions for future orientations. Concerning the deep disposal option, under the responsibility of ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), the construction of an underground laboratory has been authorized on the Bure site, in eastern France, and the shafts are under construction. The main issue is the level of investigations that may be performed in the host rock in order to support the feasibility study of a disposal concept on this site. Other issues are the elaboration of new safety standards to set a framework for a safety assessment of a disposal concept, the specifications for acceptance of waste packages in a future deep disposal, and relation of safety matters with

  18. The general situation of clay site for high-level waste geological disposal repository

    International Nuclear Information System (INIS)

    Wang Changxuan; Liu Xiaodong; Liu Pinghui

    2008-01-01

    Host medium is vitally important for safety of high-level radiaoactive waste (HLW) geological disposal. Clay, as host media of geological repository of HLW, has received greater attention for its inherent advantages. This paper summarizes IAEA and OECD/NEA's some safety guides on site selection and briefly introduces the process of the site selection, their studies and the characteristics of the clay formations in Switz-erland, France and Belgian. Based on these analyses, some suggestions are made to China's HLW repository clay site selection. (authors)

  19. Identification of scenarios in the safety assessment of a deep geological site for radioactive waste disposal

    International Nuclear Information System (INIS)

    Escalier des Orres, P.; Devillers, C.; Cernes, A.

    1990-01-01

    The selection and qualification procedure of a site for radioactive wastes disposal in a deep geologic formation, has begun in France in the early eighties. The public authorities, on ANDRA's proposal, has preselected in 1987 four sites, each of them corresponding to a type of geologic formations (granite, clay, salt and shale). Within two years, one of these sites will be chosen for the location of an underground laboratory. The safety analysis for the site's qualification uses evolution scenarios of the repository and its environment, chosen according to a deterministic method. With an appropriate detail level, are defined a reference scenario and scenario with random events. 4 refs., 1 tab [fr

  20. 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)

  1. A new safety concept for geological disposal in Japan (II) - 59357

    International Nuclear Information System (INIS)

    Kitayama, Kazumi

    2012-01-01

    This paper provides further discussion of a new defence-in-depth safety concept that was presented at ICEM09[1]. The basic idea is that it is rational to assume that the performance of passive engineered barriers with suitably chosen characteristics and the natural barrier will maintain their safety functions for a sufficiently long time due to geochemical buffering occurring deep underground, The approach can be used to enhance and embed public understanding of the long-term safety of geological disposal. This paper summarizes the logic of the approach focusing on the following topics, which are the basic themes of the new safety concept. 1. Applicability of the defence-in-depth concept to the geological disposal of radioactive waste; 2. Natural Analogue approach to explaining the long-term behaviour of the barriers; and 3. Approach for the Social Dialogue with stakeholder, which is the most important issue for site selection. (authors)

  2. NWTS program criteria for mined geologic disposal of nuclear wasite: site performance criteria

    International Nuclear Information System (INIS)

    1981-02-01

    This report states ten criteria governing the suitability of sites for mined geologic disposal of high-level radioactive waste. The Department of Energy will use these criteria in its search for sites and will reevaluate their use when the Nuclear Regulatory Commission issues radioactive waste repository rules. These criteria encompass site geometry, geohydrology, geochemistry, geologic characteristics, tectonic environment, human intrusion, surface characteristics, environment, and potential socioeconomic impacts. The contents of this document include background discussion, site performance criteria, and appendices. The background section describes the waste disposal system, the application of the site criteria, and applicable criteria from NWTS-33(1) - Program Objectives, Functional Requirements and System Performance Criteria. Appendix A, entitled Comparison with Other Siting Criteria compares the NWTS criteria with those recommended by other agencies. Appendix B contains DOE responses to public comments received on the January 1980 draft of this document. Appendix C is a glossary

  3. Electrochemical and corrosion properties of carbon steel in simulated geological disposal environments

    International Nuclear Information System (INIS)

    Sugimoto, Katsuhisa

    2011-01-01

    This paper reviews electrochemical and corrosion studies on the application of carbon steel to an overpack container, which is used for the geological disposal of radioactive wastes. Deaerated alkaline Na 2 SO 4 -NaHCO 3 - NaCl solutions and bentonite soaked with the solutions are used as simulated geological disposal environments. Electrochemical studies show the corrosion of the steel in an early stage is the activation control. Corrosion rates are controlled by the composition of the solutions, alloying elements, and the structure of the steel. The rates decrease with time due to the formation of FeCO 3 (siderite) film on the steel. Immersion corrosion tests show general corrosion morphology. Average corrosion rates of long duration have been evaluated. Clear proofs of the initiation of localized corrosion, such as pitting, crevice corrosion, hydrogen embrittlement and stress-corrosion cracking, have not been reported. (author)

  4. 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)

  5. Reference spent fuel and its characteristics for the concept development of a deep geological disposal system

    International Nuclear Information System (INIS)

    Kang, C. H.; Choi, J. W.; Ko, W. I.; Lee, Y. M.; Park, J. H.; Hwang, Y. S.; Kim, S. K.

    1997-09-01

    The total amount of spent fuel arisen from the nuclear power plant to be planned by 2010 at the basis of the long-term power development plan announced by MOTIE (Ministry of Trade, Industry and Energy Resource) in 1995 is estimated to derive the disposal capacity of a deep geological repository is derived. The reference spent fuel whose characteristics could be planned is selected by analysing the characteristic data such as initial enrichment, discharge burnup, geometry, dimension, gross weight, etc. Also isotopic concentration, radioactivity, decay heat, hazard index and radiation intensity of a reference spent fuel are quantitatively identified and summarized in order to apply in the concept developing works of a deep geological disposal system. (author). 12 refs., 24 tabs., 14 figs

  6. Reference spent fuel and its characteristics for the concept development of a deep geological disposal system

    Energy Technology Data Exchange (ETDEWEB)

    Kang, C. H.; Choi, J. W.; Ko, W. I.; Lee, Y. M.; Park, J. H.; Hwang, Y. S.; Kim, S. K.

    1997-09-01

    The total amount of spent fuel arisen from the nuclear power plant to be planned by 2010 at the basis of the long-term power development plan announced by MOTIE (Ministry of Trade, Industry and Energy Resource) in 1995 is estimated to derive the disposal capacity of a deep geological repository is derived. The reference spent fuel whose characteristics could be planned is selected by analysing the characteristic data such as initial enrichment, discharge burnup, geometry, dimension, gross weight, etc. Also isotopic concentration, radioactivity, decay heat, hazard index and radiation intensity of a reference spent fuel are quantitatively identified and summarized in order to apply in the concept developing works of a deep geological disposal system. (author). 12 refs., 24 tabs., 14 figs.

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

    International Nuclear Information System (INIS)

    Mizutani, Kazuhiko; Hiramoto, Masayuki; Morita, Atsushi

    2008-01-01

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

  8. Standard guide for characterization of spent nuclear fuel in support of geologic repository disposal

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF. 1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product c...

  9. Some notes on the Timing of Geological Disposal of CANDU Spent Fuels

    International Nuclear Information System (INIS)

    Choi, Heui Joo; Kook, Dong Hak; Choi, Jong Won

    2010-01-01

    CANDU spent fuel is to be disposed of at repository finally rather than recycled because of its low fissile nuclide concentration. But the difficult situation of finding a repository site can not help introducing a interim storage in the short term. It is required to find an optimum timing of geological disposal of CANDU spent fuels related to the interim storage operation period. The major factors for determining the disposal starting time are considered as safety, economics, and public acceptance. Safety factor is compared in terms of the decay heat and non-proliferation. Economics factor is compared from the point of the operation cost, and public acceptance factor is reviewed from the point of retrievability and inter-generation ethics. This paper recommended the best solution for the disposal starting time by analyzing the above factors. It is concluded that the optimum timing for the CANDU spent fuel disposal is around 2041 and that the sooner disposal time, the better from the point of technical and safety aspects.

  10. Principles of geological substantiation for toxic waste disposal facilities sites selection

    International Nuclear Information System (INIS)

    Khrushchov, D. P.; Matorin, Eu. M.; Shekhunova, S. B.

    2002-01-01

    Industrial, domestic and military activities result in accumulation of toxic and hazardous waste. Disposal of these waste comprises two main approaches: technological processing (utilization and destruction) and landfill. According to concepts and programs of advanced countries technological solutions are preferable, but in fact over 70 % of waste are buried in storages, prevailingly of near surface type. The target of this paper is to present principles of geological substantiation of sites selection for toxic and hazardous waste isolation facilities location. (author)

  11. MINED GEOLOGIC DISPOSAL SYSTEM (MGDS) MONITORING AND CONTROL SYSTEMS CENTRALIZATION TECHNICAL REPORT

    International Nuclear Information System (INIS)

    M.J. McGrath

    1998-01-01

    The objective of this report is to identify and document Mined Geologic Disposal System (MGDS) requirements for centralized command and control. Additionally, to further develop the MGDS monitoring and control functions. This monitoring and control report provides the following information: (1) Determines the applicable requirements for a monitoring and control system for repository operations and construction (excluding Performance Confirmation). (2) Makes a determination as to whether or not centralized command and control is required

  12. The experiment of affective web risk communication on HLW geological disposal

    International Nuclear Information System (INIS)

    Kugo, Akihide; Yoshikawa, Eiwa; Wakabayashi, Yasunaga; Shimoda, Hiroshi; Uda, Akinobu; Ito, Kyoko

    2006-01-01

    Dialog mode web contents regarding the HLW risk is effective to altruism. To make it more effectively, we introduced affective elements such as facial expression of character agents and sympathetic response on the BBS by experts, which brought us smooth risk communication. This paper describes the result of preliminary experiments surrounding the affective ways to communicate on the risk of HLW geological disposal, leading to enhance the social cooperation, and the public open experiment for one month on the Web. (author)

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

    International Nuclear Information System (INIS)

    1982-01-01

    The study of the ''Admissible thermal loading in geological formations and its consequence on radioactive waste disposal methods'' comprises four volumes: Volume 1. ''Synthesis report'' (English/French text). Volume 2. Granite formations (French text). Volume 3. Salt formations (German text). Volume 4. Clay formations (French text). The present ''synthesis report'' brings together the formation produced by the three specific studies dealing with granite, salt and clay

  14. Radionuclide migration study in the case of a geological disposal site. Bibliographic research report

    International Nuclear Information System (INIS)

    Rio, Sophie

    1997-01-01

    The present bibliographic research deals with the study of radionuclide migration in the case of a geological disposal of spent fuel from PWR nuclear reactors. Bibliography was made with the DIALOG server on the following databases: INSPEC, NTIS, Ei Compendex Plus, SPIN, SciSearch, Pascal et Current Contents Search, and with the INIS and DocTheses CD-Roms. A synthesis based on a few documents is made in the second part of the report. (author) [fr

  15. 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 ..

  16. Nuclear wastes management. 1. round table - geologic disposal as questioned by the public in concern

    International Nuclear Information System (INIS)

    2005-01-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the debates of the last round table held at Paris. This meeting gathers representatives of the different actors of the nuclear industry, ministers, public authorities, non governmental organizations who argue the questions asked by peoples from the audience. The topics concern various aspects of waste management, like the quantity of wastes in concern, the reversibility of storages, the monitoring of waste facilities once closed down, the related costs, and the general safety questions about the suitability of the clay formation near the Bure site for the disposal of high-level and long-lived radioactive wastes. A second part of the meeting addresses some remarks about the information of the general public and the decision making process. Finally, five presentations (slides) are attached to these proceedings and treat of: the safety of the disposal in deep geologic formation; the management of spent fuels in Canada; the nuclear wastes R and D in Sweden; the researches and projects in Belgium for the geologic disposal of long-lived radioactive wastes; the results

  17. 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)

  18. ICRP PUBLICATION 122: radiological protection in geological disposal of long-lived solid radioactive waste.

    Science.gov (United States)

    Weiss, W; Larsson, C-M; McKenney, C; Minon, J-P; Mobbs, S; Schneider, T; Umeki, H; Hilden, W; Pescatore, C; Vesterlind, M

    2013-06-01

    This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission's three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time 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

  19. ICRP PUBLICATION 122: Radiological Protection in Geological Disposal of Long-lived Solid Radioactive Waste

    International Nuclear Information System (INIS)

    Weiss, W.; Larsson, C-M.; McKenney, C.; Minon, J-P.; Mobbs, S.; Schneider, T.; Umeki, H.; Hilden, W.; Pescatore, C.; Vesterlind, M.

    2013-01-01

    This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission’s three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time 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

  20. Technical development for geological disposal of high-level radioactive wastes

    International Nuclear Information System (INIS)

    Asano, Hidekazu; Sugino, Hiroyuki; Kawakami, Susumu; Yamanaka, Yumiko

    1997-01-01

    Technical developments for geological disposal of high-level radioactive wastes materials research and design technique for engineered barriers (overpack and buffer material) were studied to evaluate more reliable disposal systems for high-level radioactive wastes. A lifetime prediction model for the maximum corrosion depth of carbon steel was developed. A preferable alloys evaluation method for crevice corrosion was established for titanium. Swelling pressure and water permeability of bentonite as a buffer material was measured, and coupled hydro-thermo-mechanical analysis code for bentonite was also studied. The CIP (cold isostatic pressing) method for monolithically formed buffer material was tested. A concept study on operation equipment for the disposal site was performed. Activities of microorganisms involved in underground performance were investigated. (author)

  1. 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)

  2. AERE contracts with DoE on the treatment and disposal of intermediate level wastes

    International Nuclear Information System (INIS)

    Partridge, B.A.

    1984-06-01

    This document reports work carried out in 1983/84 under 10 contracts between DoE and AERE on the treatment and disposal of intermediate level wastes. Individual summaries are provided for each contract report within the document, under the headings: comparative evaluation of α and βγ irradiated medium level waste forms; modelling and characterisation of intermediate level waste forms based on polymers; optimisation of processing parameters for polymer and bitumen modified cements; ceramic waste forms; radionuclide release during leaching; ion exchange processes; electrical processes for the treatment of medium active liquid wastes; fast reactor fuel element cladding; dissolver residues; flowsheeting/systems study. (U.K.)

  3. Evaluation of influence of splay fault growth on groundwater flow around geological disposal system

    International Nuclear Information System (INIS)

    Takai, Shizuka; Takeda, Seiji; Sakai, Ryutaro; Shimada, Taro; Munakata, Masahiro; Tanaka, Tadao

    2017-01-01

    In geological disposal, the direct effect of active faults on geological repositories is avoided at the stage of site characterization, however, uncertainty remains for the avoidance of faults derived from active faults, which are concealed deep under the ground and are difficult to detect by site investigation. In this research, the influence of the growth of undetected splay faults on a natural barrier in a geological disposal system due to the future action of faults was evaluated. We investigated examples of splay faults in Japan and set conditions for the growth of splay faults. Furthermore, we assumed a disposal site composed of sedimentary rock and made a hydrogeological model of the growth of splay faults. We carried out groundwater flow analyses, changing parameters such as the location and depth of the repository and the growth velocity of splay faults. We carried out groundwater flow analyses, changing parameters such as the location and depth of the repository and the growth velocity of splay faults. The results indicate that the main flow path from the repository is changed into an upward flow along the splay fault due to its growth and that the average velocity to the ground surface becomes one or two orders of magnitude higher than that before its growth. The results also suggest that splay fault growth leads to the possibility of the downward flow of oxidizing groundwater from the ground surface area. (author)

  4. 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. A comprehensive safety assessment program has been established which will proceed on a schedule consistent with the start-up of two waste repositories in late 1985. 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 around waters for hundreds of thousands of years. The long-term stability of each site must be demonstrated by sophisticated rock mechanics analyses. To help provide answers on the mechanism and consequences of an unlikely breach in the integrity of the repository, a Waste Isolation Safety Assessment Program (WISAP) is being sponsored at the Battelle Pacific Northwest Laboratories. Methods and data necessary to characterize the safety of generic geological waste disposal concepts, which are to be applied in the assessment of specific sties, will be developed. Other long-term safety-related studies that complement WISAP are in progress, for example, borehole plugging, salt dissolutioning, and salt transport in vertical boreholes. Requirements for licensing are in the process of being formulated by the NRC

  5. Federal fees and contracts for storage and disposal of spent LWR fuel

    International Nuclear Information System (INIS)

    Clark, H.J.

    1979-01-01

    The methodology for establishing a fee for federal spent fuel storage and disposal services is explained along with a presentation of the cost centers and cost data used to calculate the fee. Results of the initial fee calculation and the attendant sensitivity studies are also reviewed. The current status of the fee update is presented. The content of the proposed contract for federal services is briefly reviewed

  6. 2005 dossier: granite. Tome: phenomenological evolution of the geologic disposal; Dossier 2005: Granite. Tome evolution phenomenologique du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

  7. 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)

  8. In situ experiments for disposal of radioactive wastes in deep geological formations

    International Nuclear Information System (INIS)

    1987-12-01

    This report reviews the current status of in-situ experiments undertaken to assess various concepts for disposal of spent fuel and reprocessed high-level waste in deep geological formations. Specifically it describes in-situ experiments in three geological formations - clay, granite and domed salt. The emphasis in this report is on the in-situ experiments which deal with the various issues related to the near-field effects in a repository and the geological environment immediately surrounding the repository. These near-field effects are due to the disturbance caused by both the construction of the repository and the waste itself. The descriptions are drawn primarily from four underground research facilities: the Underground Experimental Facility, Belgium (clay), the Stripa Project, Sweden and the Underground Research Laboratory, Canada (granite) and the Asse Mine, Federal Republic of Germany (salt). 54 refs, figs and tab

  9. 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

  10. Factors affecting public and political acceptance for the implementation of geological disposal

    International Nuclear Information System (INIS)

    2007-10-01

    This publication identifies conditions which affect (either increase or decrease) public concern for and political acceptance of the development and implementation of programmes for geological disposal of long lived radioactive waste. It also looks at how interested citizens can be associated in the decision making process in such a way that their input enriches the outcome of a more socially robust and sustainable solution. The publication also considers how to optimize risk management, addressing the needs and expectations of the public and of other relevant stakeholders. Factors of relevance for societal acceptance conditions are identified for the different stages of a repository programme and implementation process, from policy development to the realization of the repository itself. Further, they are described and analysed through case studies from several countries, illustrating the added value of broadening the technical dimension with social dialogue and insight into value judgements.This report focuses on a geological disposal approach that consists of isolating radioactive wastes deep underground in a mined repository. It is not suggested here that geological disposal is the sole strategy that may be chosen or carried out by a country for managing high level radioactive waste, long lived waste or spent nuclear fuel. However, the geological disposal approach is favoured in principle by many countries for it is seen to offer advantages in terms of safety and security of this category of radioactive materials, and as a way to address ethical concerns. This report is meant for decision makers and others with a role in bringing forward a national programme to manage radioactive waste. Through different case studies, this report describes how programme acceptance has been fostered or hindered in different countries. It reviews factors that may affect whether a programme to develop and implement geological disposal strategy gains (or does not gain) societal

  11. RD and D steering of a geological disposal programme in poorly indurated clays

    International Nuclear Information System (INIS)

    Capouet, M.; Depaus, C.; Van Geet, M.; Lalieux, P.

    2014-01-01

    For more than thirty years, Belgium has been investigating clay formations for its potential suitability to host a geological disposal. The R and D programme initiated as early as 1974 by the Belgian Nuclear Research Centre (SCK.CEN) at Mol was pursued from the early 1980's under ONDRAF/NIRAS' responsibility. These studies quickly focused on the Boom Clay formation at Mol-Dessel, in north-eastern Belgium, as a potential host formation for a geological repository. The state of scientific and technical research on the possible disposal of high- and intermediate-level radioactive waste (B and C waste) in clay layers was presented in decennial safety assessment reports. The national and international peer review of the second Safety and Feasibility interim report SAFIR 2 acknowledged the maturity of the Belgian scientific programme and endorsed ONDRAF/NIRAS' conclusion to pursue the RD and D programme associated with a safe and feasible geological disposal in poorly indurated clays. Next to the continuing necessity of RD and D in all relevant areas of the Belgian programme, the NEA International Review Team (IRT) highlighted three main areas of activity that ONDRAF/NIRAS should strengthen to move on to the implementation phase. First, the IRT acknowledged the novel and innovative methodological concepts (i.e. safety functions, alternative safety indicators) introduced in its programme and recommended that ONDRAF/NIRAS move forward in this direction and improve the methodology for a more systematic, consistent and comprehensive treatment of uncertainties. Secondly, the IRT recommended further development of the EBS. Understanding of the engineered component's behaviour, its physic-chemical evolution with its inter-dependencies with the other components, its feasibility as well as its performance was indeed limited at the time of SAFIR 2. Last, the maturity of the geological programme suggested that it was time to initiate a dialogue with the regulators, policy makers

  12. Performance monitoring of an improved disposal trench in a humid environment in a fractured geology

    International Nuclear Information System (INIS)

    Mills, D.; Razor, J.

    1988-01-01

    An engineering evaluation of an improved disposal trench at the Maxey Flats Waste Disposal Site is being conducted in order to demonstrate the feasibility of a burial trench suitable for use at a site in a humid environment and underlain by complex and fractured geologic media. This demonstration is one of several proposed final site stabilization alternatives which will have to be evaluated prior to final site closure. Due to requirements in the Central Midwest Compact Commission, no waste generated as a result of the site closure may be disposed in the Commission's disposal site. Hence, the waste will be disposed on-site. The demonstration trench was constructed and filled with waste during the fall of 1985 with final trench capping being completed in July 1986. Since that time the trench has been evaluated utilizing trench settlement monument elevations, leachate production measurements, leachate radionuclide analysis, chemical tracer analysis and trench water balance. Measurements performed to date indicated that the trench lower infiltration barrier has a permeability of about 1E-7 cm/sec. Water balance measurements indicated that less than one percent of the total rainfall crossed the trench capillary barrier. No settlement of the trench cap has been observed. No liquid has appeared in the leachate collection and monitoring sumps

  13. Thermal analysis in the near field for geological disposal of high-level radioactive waste. Establishment of the disposal tunnel spacing and waste package pitch on the 2nd progress report for the geological disposal of HLW in Japan

    International Nuclear Information System (INIS)

    Taniguchi, Wataru; Iwasa, Kengo

    1999-11-01

    For the underground facility of the geological disposal of high-level radioactive waste (HLW), the space is needed to set the engineered barrier, and the set engineered barrier and rock-mass of near field are needed to satisfy some conditions or constraints for their performance. One of the conditions above mentioned is thermal condition arising from heat outputs of vitrified waste and initial temperature at the disposal depth. Hence, it is needed that the temperature of the engineered barrier and rock mass is less degree than the constraint temperature of each other. Therefore, the design of engineered barrier and underground facility is conducted so that the temperature of the engineered barrier and rock mass is less degree than the constraint temperature of each other. One of these design is establishment of the disposal tunnel spacing and waste package pitch. In this report, thermal analysis is conducted to establish the disposal tunnel spacing and waste package pitch to satisfy the constraint temperature in the near field. Also, other conditions or constraints for establishment of the disposal tunnel spacing and waste package pitch are investigated. Then, design of the disposal tunnel spacing and waste package pitch, considering these conditions or constraints, is conducted. For the near field configuration using the results of the design above mentioned, the temperature with time dependency is studied by analysis, and then the temperature variation due to the gaps, that will occur within the engineered barrier and between the engineered barrier and rock mass in setting engineered barrier in the disposal tunnel or pit, is studied. At last, the disposal depth variation is studied to satisfy the temperature constraint in the near field. (author)

  14. The analysis of geological formations from Romania available for disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Alecu, Catalin

    2003-01-01

    The majority of countries possessing nuclear power industry has not yet decided upon the option about closing the nuclear cycle. There are still in progress projects concerning the final disposal, while worldwide it is not foreseen the reprocessing of the whole amount of reusable fissionable materials. The annual worldwide production of used nuclear fuel continues to be about 10 500 - 11 000 tones of heavy metal. The difficulties in designing used fuel final disposal repositories led to the design of some interim storage facilities, providing a satisfactory safety level for biosphere. On the other hand, regardless of the selected option we respect to closing the nuclear cycle, a final repository must exists, either for the high level wastes resulted from reprocessing the used nuclear fuel or for the used fuel considered radioactive waste. Although, presently, in Romania, the nuclear fuel extracted from the reactor after its 'useful life' is declared as radioactive waste, it may contain a certain amount of fissionable material that could be used in other types of reactors. This possibility implies taking into account the concept regarding the recovery of fuel after a certain period of time, although, by definition, final disposal means prevention of this possibility. The harmonization of the Romanian legislation with that of the European Community and the adhering to the European Conventions, poses among other issues the problem of the final disposal of the used nuclear fuel. Starting from these major requirements the paper presents the main aspects of the Project 011/11.10.2001, entitled 'Researches for the selection and preliminary characterization of the host rock for the final disposal of the used nuclear fuel', part of The National Research Program: Medium, Energy and Resources. A complex analysis regarding the implications on the design of the Used Nuclear Fuel Final Disposal Repository in Romania was performed, the analysis of the available geological

  15. Reversed mining and reversed-reversed mining: the irrational context of geological disposal of nuclear waste

    Science.gov (United States)

    van Loon, A. J.

    2000-06-01

    Man does not only extract material from the Earth but increasingly uses the underground for storage and disposal purposes. One of the materials that might be disposed of this way is high-level nuclear waste. The development of safe disposal procedures, the choice of suitable host rocks, and the design of underground facilities have taken much time and money, but commissions in several countries have presented reports showing that — and how — safe geological disposal will be possible in such a way that definite isolation from the biosphere is achieved. Political views have changed in the past few years, however, and there is a strong tendency now to require that the high-level waste disposed of will be retrievable. Considering the underlying arguments for isolation from the biosphere, and also considering waste policy in general, this provides an irrational context. The development of new procedures and the design of new disposal facilities that allow retrieval will take much time again. A consequence may be that the high-active, heat-generating nuclear waste will be stored temporarily for a much longer time than objectively desirable. The delay in disposal and the counterproductive requirement of retrievability are partly due to the fact that earth-science organisations have failed to communicate in the way they should, possibly fearing public (and financial) reactions if taking a position that is (was?) considered as politically incorrect. Such an attitude should not be maintained in modern society, which has the right to be informed reliably by the scientific community.

  16. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 1. Geological environment of Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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 1 of the progress report, describes first in detail the role of geological environment in high-level radioactive wastes disposal, the features of Japanese geological environment, and programs to proceed the investigation in geological environment. The following chapter summarizes scientific basis for possible existence of stable geological environment, stable for a long period needed for the HLW disposal in Japan including such natural phenomena as volcano and faults. The results of the investigation of the characteristics of bed-rocks and groundwater are presented. These are important for multiple barrier system construction of deep geological disposal. The report furthermore describes the present status of technical and methodological progress in investigating geological environment and finally on the results of natural analog study in Tono uranium deposits area. (Ohno, S.)

  17. Road-map to successful implementation of geological disposal in the EU

    International Nuclear Information System (INIS)

    Patrakka, Eero

    2010-01-01

    In the conclusions from its first meeting in Bratislava (2007), the European Nuclear Energy Forum (ENEF) identified the management of spent fuel and radioactive waste as an important subject to be looked into with the objective 'to encourage Member States and industry to swiftly implement adequate nuclear waste disposal facilities, in particular deep geological repositories for high level waste'. To this end the Sub-Working Group 'Waste Management' (SWG-WM) was created in the context of the ENEF Working Group 'Risks'. As a first task, the SWG-WM was requested to compile a road-map that includes the essential elements of what is required at national level to foster the implementation of geological disposal for high level waste and spent fuel. In October 2009, a 'Road-map to Successful Implementation of Geological Disposal in the EU' was endorsed. The aim of this document is to provide guidance to EU Member States that are starting out or are at an early stage on the decades-long process leading towards the implementation of geological repositories for high level radioactive wastes or spent nuclear fuel, if this is deemed to be a waste. The guidance is based to a large extent on the positive progress that has been made in a number of Member States. Small and new nuclear states may take a long time to reach such a position - but a strong message of this Road-map is that the process should be initiated as soon as possible. The Road-map is intended to be generic enough to be applicable to all Member States, independently of their current position; the national Road-maps to be developed should be compatible with this, but will differ in the specifics of approach and of timing. (authors)

  18. Study on systematic integration technology of design and safety assessment for HLW geological disposal. 2. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito, Takaya; Kohanawa, Osamu; Kuwayama, Yuki

    2003-02-01

    The present study was carried out relating to basic design of the Geological Disposal Technology Integration System' that will be systematized as knowledge base for design analysis and safety assessment of HLW geological disposal system by integrating organically and hierarchically various technical information in three study field. The key conclusions are summarized as follows: (1) As referring to the current performance assessment report, the technical information for R and D program of HLW geological disposal system was systematized hierarchically based on summarized information in a suitable form between the work flow (work item) and processes/characteristic flow (process item). (2) As the result of the systematized technical information, database structure and system functions necessary for development and construction to the computer system were clarified in order to secure the relation between technical information and data set for assessment of HLW geological disposal system. (3) The control procedure for execution of various analysis code used by design and safety assessment in HLW geological disposal study was arranged possibility in construction of 'Geological Disposal Technology Integration System' after investigating the distributed computing technology. (author)

  19. 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.

  20. Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Rempe, N.T.

    1993-01-01

    Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600 m thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope - amounting to about a quarter million years, the time during which its activity will decline to background level represent only 0.11 percent of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible

  1. CIGeO geological disposal for high-level radioactive waste in France

    International Nuclear Information System (INIS)

    Ouzounian, Gerald; Bolia, Jelana

    2014-01-01

    Andra is the sole French organization responsible for the radioactive waste management in the country. Its work relies extensively on the legal basis provided by several major laws (Waste Act of 1991 and the Planning Act of 2006), which shaped the main principles of the waste management strategy and determined the corresponding implementation tools. Andra's industrial activities are essentially based around three of its national disposal facilities. Two of these operational facilities, by their design and comprehensive monitoring system, are considered worldwide as solid and proven reference solutions for the concerned types of radioactive waste. Andra is also charged with designing a future deep geological repository for intermediate-level long-lived and high-level waste and researching potential management and disposal solutions for the graphite and radium-bearing waste. The purpose of this article is to update the information to the readers about the Cigeo geological disposal project for high-level radioactive waste in France (authors)

  2. 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.

  3. NEA perspectives on timescales and criteria in post-closure safety of geological disposal

    International Nuclear Information System (INIS)

    Preter, P. de; Smith, P.; Pescatore, C.; Forinash, B.

    2006-01-01

    A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

  4. NEA perspectives on timescales and criteria in post-closure safety of geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    Preter, P. de [ONDRAF/NIRAS, Brussels (Belgium); Smith, P. [Safety Assessment Management Ltd, SAM Ltd. (United Kingdom); Pescatore, C.; Forinash, B. [OECD/NEA, Nuclear Energy Agency, 92 - Issy les Moulineaux (France)

    2006-07-01

    A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

  5. 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.)

  6. Development of an international safeguards approach to the final disposal of spent fuel in geological repositories

    International Nuclear Information System (INIS)

    Murphey, W.M.; Moran, B.W.; Fattah, A.

    1996-01-01

    The International Atomic Energy Agency (IAEA) is currently pursuing development of an international safeguards approach for the final disposal of spent fuel in geological repositories through consultants meetings and through the Program for Development of Safeguards for Final Disposal of Spent Fuel in Geological Repositories (SAGOR). The consultants meetings provide policy guidance to IAEA; SAGOR recommends effective approaches that can be efficiently implemented by IAEA. The SAGOR program, which is a collaboration of eight Member State Support Programs (MSSPs), was initiated in July 1994 and has identified 15 activities in each of three areas (i.e. conditioning facilities, active repositories, and closed repositories) that must be performed to ensure an efficient, yet effective safeguards approach. Two consultants meetings have been held: the first in May 1991 and the last in November 1995. For nuclear materials emplaced in a geological repository, the safeguards objectives were defined to be (1) to detect the diversion of spent fuel, whether concealed or unconcealed, from the repository and (2) to detect undeclared activities of safeguards concern (e.g., tunneling, underground reprocessing, or substitution in containers)

  7. Geologic siting considerations for the disposal of radioactive waste into submarine geologic formations

    International Nuclear Information System (INIS)

    Hollister, C.D.

    1979-01-01

    The most desirable characteristics of the host medium are: (1) low permeability and high Kd; (2) ability to self heal, i.e., be visco-elastic in response to dynamic stress; (3) stability under predicted thermal loading; (4) a low content of organic matter, i.e., be well oxidized. The submarine geologic formation that appears to best satisfy the above criteria is abyssal red clay. Depending on organic interactions and permeability considerations, light brown deep-sea clays with 20 to 40% CaCO 3 also may be suitable. Increasingly organic-rich, more permeable biogenic oozes appear less suitable, with turbidite sands and silts least desirable of all. Ocean regions excluded at the present time are: (1) areas less than 4000 meters deep; (2) the continental margin including fans, deltas, aprons, cones; (3) proximal portions of abyssal plains; (4) all fracture zone abyssal plains; (5) all submarine canyon-levee systems; (6) areas covered with less than 50 meters of sediment; (7) areas greater than 100 nautical miles from plate boundaries; (8) areas with ice-rafted debris; (9) major shipping lanes, cable routes and defense installations; (10) seafloor regions below areas of high biological productivity; and (11) approximately one third of the world's ocean floor satisfy these criteria

  8. 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)

  9. Development and management of the knowledge base for the geological disposal technology. Annual report 2006

    International Nuclear Information System (INIS)

    Umeda, Koji; Oyama, Takuya; Kurosawa, Hideki; Semba, Takeshi; Takeuchi, Shinji; Tajikara, Masayoshi; Tsuruta, Tadahiko; Yasue, Ken-ichi; Ohi, Takao; Oda, Chie; Kamei, Gento; Kobayashi, Yasushi; Sasaki, Yasuo; Sawada, Atsushi; Taniguchi, Naoki; Tanai, Kenji; Naito, Morimasa; Nakayama, Masashi; Kuno, Yoshio; Fujita, Tomoo; Honda, Akira; Mihara, Morihiro; Miyahara, Kaname; Osawa, Hideaki; Fujishima, Atsushi; Kuji, Masayoshi; Saito, Haruo; Sanada, Hiroyuki; Niizato, Tadafumi; Funaki, Hironori; Maekawa, Keisuke; Fujiwara, Kenso

    2007-12-01

    To increase technical reliability in geological disposal technology of high-level radioactive waste, JAEA have been conducting R and D activities in the fields in the repository engineering, performance assessment (PA) of the geological disposal system, and geoscientific study. In the field of R and D on the repository engineering, laboratory experimental studies at Tokai Research Center are carried out by engineering-scale and non-radiogenic experiments. The studies on performance assessment include more realistic model development with extensive computer analyses and acquisition of basic data concerning the chemical properties and migration behavior of radionuclides under geological disposal conditions. The information obtained from the Underground Research Laboratories (URLs) is used to provide a realistic condition of geological environments for these studies. The R and D studies are also carried out for TRU waste. A particular JAEA R and D activity is to promote the projects of two Underground Research Laboratories (URLs): one at Mizunami city, in crystalline rock and the other at Horonobe town, in sedimentary rock. In the present stage (2nd R and D phase) of the URL projects, the investigation are being carried out during the excavation of shafts and drifts. Data obtained from the investigations will serve to verify and refine the results from the surface-based investigations and characterize the evolution of the geological environment during drift excavation. The research on natural processes, such as fault and volcanic activities, is also conducted to provide better understanding of long-term stability on the geological environment. JAEA has initiated a project to develop the next generation of novel knowledge management system (KMS) to develop and manage the technical knowledge base for supporting implementers and regulators. This knowledge base includes all technical achievements by the JAEA as well as know-how and experience which have been accumulated

  10. 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

  11. 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.)

  12. Costs and ways of financing of the geological disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Venet, P.; Haijtink, B.

    1988-01-01

    A global approach to the management of radioactive wastes must take into account not only the technological or safety aspects but also economic and financial considerations. In this study, the cost of geological disposal of radioactive wastes are initially evaluated for a certain number of representative cases of present tendencies in the European Community. These expenses comprise research, development and site validation costs, transport and interim storage costs and finally expenditure relating to various investment and exploitation phases of the disposal site as well as its closure. The possible ways of financing are subsequently reviewed and the financial charges which resulted are calculated for each considered scenario. The study is based on the most recent technical knowledge. It has been carried out by natural organizations involved in the management of radioactive wastes. ANDRA in France, CEN/SCK and ONDRAF/NIRAS in Belgium and DBE in Federal Republic of Germany on behalf of the Commission of the European Communities [fr

  13. Costs and ways of financing of the geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Venet, P.; Baetsle, L.H.; Barthoux, A.; Engelmann, H.J.

    1985-01-01

    A global approach to the management of radioactive waste must take into account not only the technological or safety aspects but also economic and financial considerations. In this study, the costs of geological disposal of radioactive waste are initially evaluated for a certain number of representative cases of present tendencies in the European Community. These expenses comprise research, development and site validation costs, transport and interim storage costs and finally expenditure relating to various investment and exploitation phases of the disposal site as well as its closure. The possible ways of financing are subsequently reviewed and the financial charges which resulted are calculated for each considered scenario. The study is based on the most recent technical knowledge. It has been carried out by national organizations involved in the management of radioactive waste: ANDRA in France, CEN/SCK and ONDRAF/NIRAS in Belgium and DBE in F.R. of Germany on behalf of the Commission of the European Communities

  14. A study on closure performance in geological disposal of high-level radioactive waste (H14)

    International Nuclear Information System (INIS)

    Sugita, Yutaka; Kawakami, Susumu; Yui, Mikazu; Makino, Hitoshi; Sawada, Atsushi; Kurihara, Yuji; Mihara, Morihiro

    2003-04-01

    Regarding closure technology of underground facilities in geological disposal of the HLW in H12 report, the fundamental concept that closure technology has no impact against the engineered barrier system (EBS) was described. Performance Assessment (PA) has been performed without considering of the barrier function of closure elements. Following H12 report, the various in-situ data of the closure elements (ex. plug, backfill) have been obtained. Therefore, we considered that the PA of the EBS considering the expecting performance of the closure elements from the view points of both the engineering technology and the PA should be examined. First, the characteristics of rock mass and the function of the closure elements were summarized. Then, the closure scenario was developed preliminarily based on hydrological analysis between a hydraulic fracture and a disposal panel, the fault tree analysis, and so on. (author)

  15. Sensitivity analysis and uncertainties simulation of the migration of radionuclide in the system of geological disposal-CRP-GEORC model

    International Nuclear Information System (INIS)

    Su Rui; Wang Ju; Chen Weiming; Zong Zihua; Zhao Honggang

    2008-01-01

    CRP-GEORC concept model is an artificial system of geological disposal for High-Level radioactive waste. Sensitivity analysis and uncertainties simulation of the migration of radionuclide Se-79 and I-129 in the far field of this system by using GoldSim Code have been conducted. It can be seen from the simulation results that variables used to describe the geological features and characterization of groundwater flow are sensitive variables of whole geological disposal system. The uncertainties of parameters have remarkable influence on the simulation results. (authors)

  16. Survey of the geological characteristics on the Japanese Islands for disposal of RI and research institute waste

    Energy Technology Data Exchange (ETDEWEB)

    Hagiwara, Shigeru [Chuo Kaihatsu Co., Ltd., Tokyo (Japan); Sakamoto, Yoshiaki; Takebe, Shinichi; Ogawa, Hiromichi; Nakayama, Shinichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-12-01

    In the disposal of radioactive wastes arising from radioisotope utilization facilities and nuclear research facilities, it is necessary to establish the disposal system in proportion to half-lives of radionuclides and radioactivity concentrations in the wastes. According to this disposal system, the radioactive waste should be buried in the underground near the surface, shallow position and deep position. Therefore, it is important to grasp the features of the earth scientific phenomena and geological structure for the disposal system of radioactive waste. Then, for the purpose of the survey of the geological characteristics around the Japanese Islands whole neighborhood, the earth scientific phenomena at present, the geological structure and geotectonic history were summarized on the basis of the existing literatures. (author)

  17. Summary of key directives governing permanent disposal in a geologic repository

    International Nuclear Information System (INIS)

    Sands, S.C. III.

    1993-11-01

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

  18. Questions on geology in connection with final radioactive waste disposal in the Fennoscandian Shield

    International Nuclear Information System (INIS)

    Bjoerklund, A.

    1990-01-01

    The use of nuclear power involves handling and disposal of radioactive waste. A number of methods for disposal have been proposed, one of which is the construction of repositories in crystalline bedrock of old continental crust. This possibility is usually considered reliable because of the relative stability of such bedrock. The Fennoscandian area has repeatedly been glaciated during the past 3 mission years. The last glacial event terminated some 10 000 years ago. This glacial ''massage'' has maintained a dense network of fractures and faults open for circulating water and ascending gas. Blocks of relatively unfractured bedrock have been proposed as suitable sites for the disposal of nuclear waste. Such questions concern neotectonic activity, the movement, salt content and amount of water at a few hundred metres depth, the mobility of elements in the bedrock as well as the geological processes which might be active beneath any future ice cap. Deep groundwaters, dating of young fracture minerals and neotectonic movements have been studied during 1985 - 1989 in a Nordic reserach program sponsored by NKA, the Nordic Liaison Committee for Atomic Energy. Deep saline groundwaters may have a negative effect on repositories of nuclear waste and the knowledge of the location of such waters may also give a hint as to the pattern of water movement in the bedrock. Therefore the composition, origin and location of deep groundwaters were studied. The development of faults in the bedrock through a site of waste disposal before the radioactivity in the waste has decayed to a safe level is considered a serious risk factor. Neotectonic movements have mostly followed old faults and fracture zones in the bedrock, which repeatedly have been reactivated during geological time, leaving blocks between the faults tectonically undisturbed. (CLS) 80 refs

  19. Developing international safety standards for the geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Metcalf, P.

    2001-01-01

    In the context of the International Atomic Energy Agency's (IAEA) programme to create a corpus of internationally accepted Radioactive Waste Safety Standards (RADWASS), focus is currently being placed on establishing standards for the 'geological disposal of radioactive waste'. This is a challenging task and to help the standards development process there is a need to stimulate discussion of some of the associated scientific and technical issues. A number of position papers developed in recent years by a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, address many of the relevant issues. These include a common safety based framework for radioactive waste disposal, appropriate time frames for safety assessment, different possible indicators of long-term safety, the safety implications of reversibility and retrievability, the assessment of possible human intrusion into the repository, the role and limitations of institutional control, establishing reference critical groups and biospheres for long-term assessment, and what is meant by 'compliance' with the standards. These papers will be discussed at a Specialists Meeting to be held at the IAEA in June 2001 as a means of establishing the extent to which they enjoy the general support of experts. In order to broaden that consensus, the conclusions reached at the Specialists Meeting on the issues listed above will be presented and discussed with participants at a number of international meetings. Later this year, a draft safety standard on the geological disposal of radioactive waste which takes account of the consensus positions reached through the various consultations will be submitted for the consideration of Waste Safety Standards Committee (WASSC), the officially approved body within the IAEA for the review and approval of waste safety standards. The Committee is made up of government appointed radioactive waste regulators

  20. A framework for elaborating a geological disposal safety case: Main issues to be addressed

    International Nuclear Information System (INIS)

    Besnus, F.; Gay, D.

    2002-01-01

    International guidance on safety standards for the geological disposal of radioactive waste is being elaborated by IAEA. A comparison of experiences acquired in developing deep repository projects shows that many important issues related to the progressive building of confidence in the safety demonstration of such facilities are commonly addressed by the various organisations involved in radioactive waste management. However, there is still some discrepancies in defining the steps that form the staged elaboration of a safety case. This paper intends to propose a framework for defining the safety case in describing the main issues to be addressed and highlighting questions of consistency between former steps. (author)

  1. Characterization of TRUW ceramics in relation to geological disposal in clay

    International Nuclear Information System (INIS)

    Iseghem, P. van

    1985-01-01

    Various waste forms are being studied in Belgium for their suitability for geological disposal, such as high-level waste glasses, alpha waste ceramics, medium level waste bitumen, and hulls incorporated in lead or concrete. In this paper, attention will be focussed on ceramics, resulting from the high temperature slagging incineration of both combustible and non-combustible alpha waste. Test runs were carried out with either simulated or Pu doped alpha waste, and with simulated or real βγ active waste. (orig./PW)

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

    International Nuclear Information System (INIS)

    Sato, Haruo

    1998-01-01

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

  3. Issues related to the construction and operation of a geological disposal facility for nuclear fuel waste in crystalline rock - the Canadian experience

    Energy Technology Data Exchange (ETDEWEB)

    Allan, C.J.; Baumgartner, P.; Ohta, M.M.; Simmons, G.R.; Whitaker, S.H. [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs

    1997-12-31

    This paper covers the overview of the Canadian nuclear fuel waste management program, the general approach to the siting, design, construction, operation and closure of a geological disposal facility, the implementing disposal, and the public involvement in implementing geological disposal of nuclear fuel waste. And two appendices are included. 45 refs., 5 tabs., 10 figs.

  4. Issues related to the construction and operation of a geological disposal facility for nuclear fuel waste in crystalline rock - the Canadian experience

    International Nuclear Information System (INIS)

    Allan, C.J.; Baumgartner, P.; Ohta, M.M.; Simmons, G.R.; Whitaker, S.H.

    1997-01-01

    This paper covers the overview of the Canadian nuclear fuel waste management program, the general approach to the siting, design, construction, operation and closure of a geological disposal facility, the implementing disposal, and the public involvement in implementing geological disposal of nuclear fuel waste. And two appendices are included. 45 refs., 5 tabs., 10 figs

  5. 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

  6. Synthesis of nuclear waste monazites, ideal actinide hosts for geologic disposal

    International Nuclear Information System (INIS)

    McCarthy, G.J.; White, W.B.; Pfoertsch, D.E.

    1978-01-01

    Monazite, an orthophosphate mineral of the lanthanides (Ln) and the actinides (An) U and Th, is a model for an ideal synthetic mineral waste form for geologic disposal of long-lived nuclear waste actinides. Natural monazites are known to have survived many of the conditions that might be inflicted on a nuclear waste repository by geological disruptions. High Th and U monazites with compositions typical of nuclear wastes have been synthesized with a routine calcination-pelletization-crystallization procedure. Charge balance for the Th 4+ → Ln 3+ substitution can be provided by either an equimolar Ca 2+ → Ln 3+ or Si 4+ → P 5+ substitution. For U 4+ → Ln 3+ , only the Ca 2+ → Ln 3+ substitution resulted in a phase-pure monazite. Unit cell parameter data were obtained for each nuclear waste monazite phase

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  8. A pragmatic view on the role of optimisation and bat in regulating geological disposal

    International Nuclear Information System (INIS)

    Dverstorp, B.

    2008-01-01

    Bjorn Dverstorp presented a pragmatic view on the role of optimisation and BAT in regulating geological disposal. He stressed that risk analyses for geological repositories will always be associated with uncertainties and it will not be possible to check the results of the performance assessment calculations. Therefore there is a need for additional supporting arguments in the safety case (or license application) to convince the regulator and to support decision making. He identified the constraints for the application of optimisation, including societal constraints on site selection, economic constraints on the availability of funds and technical constraints linked to the availability of technology and the effectiveness of various measures for enhancing the repository's protective capability. (author)

  9. Geologic disposal evaluation program semiannaul report for period ending March 31, 1975

    International Nuclear Information System (INIS)

    1975-07-01

    The Radioactive Waste Repository Project at the Oak Ridge National Laboratory has for some time been engaged in a program directed toward establishing a Federal Repository for radioactive wastes, primarily solidified high-level waste, in a bedded salt formation. Early in 1974, the project was restructured and, to more nearly reflect its broadened scope, was renamed the Geologic Disposal Evaluation (GDE) Program. This report is the first in a series of semiannual progress reports which will be issued to document the progress made in the GDE Program. Most of the subject matter discussed is either geologic or developmental in nature, as would be expected, since the engineering assessment depends on the data generated in these two areas. In addition, since this report also covers the transition period between the Radioactive Waste Repository Project (RWRP) and the GDE Program, information on several RWRP programs, is included. (U.S.)

  10. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Reneau, S.L.; Raymond, R. Jr.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau

  11. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Reneau, S.L.; Raymond, R. Jr. [eds.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

  12. A study for the safety evaluation of geological disposal of TRU waste and influence on disposal site design by change of amount of TRU waste (Joint research)

    International Nuclear Information System (INIS)

    Hasegawa, Makoto; Kondo, Hitoshi; Takahashi, Kuniaki; Funabashi, Hideaki; Kawatsuma, Shinji; Kamei, Gento; Hirano, Fumio; Mihara, Morihiro; Ueda, Hiroyoshi; Ohi, Takao; Hyodo, Hideaki

    2011-02-01

    In the safety evaluation of the geological disposal of the TRU waste, it is extremely important to share the information with the Research and development organization (JAEA: that is also the waste generator) by the waste disposal entrepreneur (NUMO). In 2009, NUMO and JAEA set up a technical commission to investigate the reasonable TRU waste disposal following a cooperation agreement between these two organizations. In this report, the calculation result of radionuclide transport for a TRU waste geological disposal system was described, by using the Tiger code and the GoldSim code at identical terms. Tiger code is developed to calculate a more realistic performance assessment by JAEA. On the other hand, GoldSim code is the general simulation software that is used for the computation modeling of NUMO TRU disposal site. Comparing the calculation result, a big difference was not seen. Therefore, the reliability of both codes was able to be confirmed. Moreover, the influence on the disposal site design (Capacity: 19,000m 3 ) was examined when 10% of the amount of TRU waste increased. As a result, it was confirmed that the influence of the site design was very little based on the concept of the Second Progress Report on Research and Development for TRU Waste Disposal in Japan. (author)

  13. Safety case development in the Japanese programme for geological disposal of HLW: Evolution in the generic stage

    International Nuclear Information System (INIS)

    Ueda, Hiroyoshi; Ishiguro, Katsuhiko; Takeuchi, Mitsuo; Fujihara, Hiroshi; Takeda, Seietsu

    2014-01-01

    In the Japanese programme for nuclear power generation, the safe management of the resulting radioactive waste, particularly vitrified high-level waste (HLW) from fuel reprocessing, has been a major concern and a focus of R and D since the late 70's. According to the specifications in a report issued by an advisory committee of the Japan Atomic Energy Commission (JAEC, 1997), the Second Progress Report on R and D for the Geological Disposal of HLW (H12 report) (JNC, 2000) was published after two decades of R and D activities and showed that disposal of HLW in Japan is feasible and can be practically implemented at sites which meet certain geological stability requirements. The H12 report supported government decisions that formed the basis of the 'Act on Final Disposal of Specified Radioactive Waste' (Final Disposal Act), which came into force in 2000. The Act specifies deep geological disposal of HLW at depths greater than 300 metres, together with a stepwise site selection process in three stages. Following the Final Disposal Act, the supporting 'Basic Policy for Final Disposal' and the 'Final Disposal Plan' were authorised in the same year. (authors)

  14. Geologic and hydrologic investigations of a potential nuclear waste disposal site at Yucca Mountain, southern Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Carr, M.D.; Yount, J.C. (eds.)

    1988-12-31

    Yucca Mountain in southern Nye County, Nevada, has been selected by the United States Department of Energy as one of three potential sites for the nation`s first high-level nuclear waste repository. Its deep water table, closed-basin ground-water flow, potentially favorable host rock, and sparse population have made the Yucca Mountain area a viable candidate during the search for a nuclear waste disposal site. Yucca Mountain, however, lies within the southern Great Basin, a region of known contemporary tectonism and young volcanic activity, and the characterization of tectonism and volcanism remains as a fundamental problem for the Yucca Mountain site. The United States Geological Survey has been conducting extensive studies to evaluate the geologic setting of Yucca Mountain, as well as the timing and rates of tectonic and volcanic activity in the region. A workshop was convened by the Geologic Survey in Denver, Colorado, on August 19, 20, and 21, 1985, to review the scientific progress and direction of these studies. Considerable debate resulted. This collection of papers represents the results of some of the studies presented at the workshop, but by no means covers all of the scientific results and viewpoints presented. Rather, the volume is meant to serve as a progress report on some of the studies within the Geological Survey`s continuing research program toward characterizing the tectonic framework of Yucca Mountain. Individual papers were processed separately for the data base.

  15. Geologic and hydrologic investigations of a potential nuclear waste disposal site at Yucca Mountain, southern Nevada

    International Nuclear Information System (INIS)

    Carr, M.D.; Yount, J.C.

    1988-01-01

    Yucca Mountain in southern Nye County, Nevada, has been selected by the United States Department of Energy as one of three potential sites for the nation's first high-level nuclear waste repository. Its deep water table, closed-basin ground-water flow, potentially favorable host rock, and sparse population have made the Yucca Mountain area a viable candidate during the search for a nuclear waste disposal site. Yucca Mountain, however, lies within the southern Great Basin, a region of known contemporary tectonism and young volcanic activity, and the characterization of tectonism and volcanism remains as a fundamental problem for the Yucca Mountain site. The United States Geological Survey has been conducting extensive studies to evaluate the geologic setting of Yucca Mountain, as well as the timing and rates of tectonic and volcanic activity in the region. A workshop was convened by the Geologic Survey in Denver, Colorado, on August 19, 20, and 21, 1985, to review the scientific progress and direction of these studies. Considerable debate resulted. This collection of papers represents the results of some of the studies presented at the workshop, but by no means covers all of the scientific results and viewpoints presented. Rather, the volume is meant to serve as a progress report on some of the studies within the Geological Survey's continuing research program toward characterizing the tectonic framework of Yucca Mountain. Individual papers were processed separately for the data base

  16. Radiological impact of a spent fuel disposal in a deep geological granite formation - results of the european spa project

    International Nuclear Information System (INIS)

    Baudoin, P.; Gay, D.; Certes, C.; Serres, C.

    2000-01-01

    The SPA project (Spent fuel disposal Performance Assessment) is the latest of four integrated performance assessment exercises on nuclear waste disposal in geological formations, carried out in the framework of the European Community 'Nuclear Fission' Research Programmes. The SPA project, which was undertaken by ENRESA, GRS, IPSN, NRG, SCK.CEN and VTT between May 1996 and April 1999, was devoted to the study of disposal of spent fuel in various host rock formations (clay, crystalline rocks and salt formation). This project is a direct continuation of the efforts made by the European Community since 1982 to build a common understanding of the methods applicable to deep disposal performance assessment. (authors)

  17. Regional Geologic Evaluations for Disposal of HLW and SNF: The Pierre Shale of the Northern Great Plains

    Energy Technology Data Exchange (ETDEWEB)

    Perry, Frank Vinton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kelley, Richard E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-14

    The DOE Spent Fuel and Waste Technology (SWFT) R&D Campaign is supporting research on crystalline rock, shale (argillite) and salt as potential host rocks for disposal of HLW and SNF in a mined geologic repository. The distribution of these three potential repository host rocks is limited to specific regions of the US and to different geologic and hydrologic environments (Perry et al., 2014), many of which may be technically suitable as a site for mined geologic disposal. This report documents a regional geologic evaluation of the Pierre Shale, as an example of evaluating a potentially suitable shale for siting a geologic HLW repository. This report follows a similar report competed in 2016 on a regional evaluation of crystalline rock that focused on the Superior Province of the north-central US (Perry et al., 2016).

  18. 2005 dossier: granite. Tome: architecture and management of the geologic disposal; Dossier 2005: granite. Tome architecture et gestion du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

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

  19. Regulating the long-term safety of geological disposal of radioactive waste: practical issues and challenges

    International Nuclear Information System (INIS)

    2008-01-01

    Regulating the long-term safety of geological disposal of radioactive waste is a key part of making progress on the radioactive waste management issue. A survey of member countries has shown that differences exist both in the protection criteria being applied and in the methods for demonstrating compliance, reflecting historical and cultural differences between countries which in turn result in a diversity of decision-making approaches and frameworks. At the same time, however, these differences in criteria are unlikely to result in significant differences in long-term protection, as all the standards being proposed are well below levels at which actual effects of radiological exposure can be observed and a range of complementary requirements is foreseen. In order to enable experts from a wide range of backgrounds to debate the various aspects of these findings, the NEA organised an international workshop in November 2006 in Paris, France. Discussions focused on diversity in regulatory processes; the basis and tools for assuring long-term protection; ethical responsibilities of one generation to later generations and how these can be discharged; and adapting regulatory processes to the long time frames involved in implementing geological disposal. These proceedings include a summary of the viewpoints expressed as well as the 22 papers presented at the workshop. (author)

  20. Natural setting of Japanese islands and geologic disposal of high-level waste

    International Nuclear Information System (INIS)

    Koide, Hitoshi

    1991-01-01

    The Japanese islands are a combination of arcuate islands along boundaries between four major plates: Eurasia, North America, Pacific and Philippine Sea plates. The interaction among the four plates formed complex geological structures which are basically patchworks of small blocks of land and sea-floor sediments piled up by the subduction of oceanic plates along the margin of the Eurasia continent. Although frequent earthquakes and volcanic eruptions clearly indicate active crustal deformation, the distribution of active faults and volcanoes is localized regionally in the Japanese islands. Crustal displacement faster than 1 mm/year takes place only in restricted regions near plate boundaries or close to major active faults. Volcanic activity is absent in the region between the volcanic front and the subduction zone. The site selection is especially important in Japan. The scenarios for the long-term performance assessment of high-level waste disposal are discussed with special reference to the geological setting of Japan. The long-term prediction of tectonic disturbance, evaluation of faults and fractures in rocks and estimation of long-term water-rock interaction are key issues in the performance assessment of the high-level waste disposal in the Japanese islands. (author)

  1. Characterizing fractured plutonic rocks of the Canadian shield for deep geological disposal of Canada's radioactive wastes

    International Nuclear Information System (INIS)

    Lodha, G.S.; Davison, C.C.; Gascoyne, M.

    1998-01-01

    Since 1978 AECL has been investigating plutonic rocks of the Canadian Shield as a potential medium for the disposal of Canada's nuclear fuel waste. During the last two years this study has been continued as part of Ontario Hydro's used fuel disposal program. Methods have been developed for characterizing the geotechnical conditions at the regional scale of the Canadian Shield as well as for characterizing conditions at the site scale and the very near-field scale needed for locating and designing disposal vault rooms and waste emplacement areas. The Whiteshell Research Area (WRA) and the Underground Research Laboratory (URL) in southeastern Manitoba have been extensively used to develop and demonstrate the different scales of characterization methods. At the regional scale, airborne magnetic and electromagnetic surveys combined with LANDSAT 5 and surface gravity survey data have been helpful in identifying boundaries of the plutonic rocks , overburden thicknesses, major lineaments that might be geological structures, lithological contacts and depths of the batholiths. Surface geological mapping of exposed rock outcrops, combined with surface VLF/EM, radar and seismic reflection surveys were useful in identifying the orientation and depth continuity of low-dipping fracture zones beneath rock outcrops to a depth of 500 to 1000 m. The surface time-domain EM method has provided encouraging results for identifying the depth of highly saline pore waters. The regional site scale investigations at the WRA included the drilling of twenty deep boreholes (> 500 m) at seven separate study areas. Geological core logging combined with borehole geophysical logging, TV/ATV logging, flowmeter logging and full waveform sonic logging in these boreholes helped to confirm the location of hydro geologically important fractures, orient cores and infer the relative permeability of some fracture zones. Single-hole radar and crosshole seismic tomography surveys were useful to establish the

  2. International Approaches for Nuclear Waste Disposal in Geological Formations: Report on 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); Persoff, Peter [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sassani, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Swift, Peter N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-08-01

    An important issue for present and future generations is the final disposal of spent nuclear fuel. Over the past over forty years, the development of technologies to isolate both spent nuclear fuel (SNF) and other high-level nuclear waste (HLW) generated at nuclear power plants and from production of defense materials, and low- and intermediate-level nuclear waste (LILW) in underground rock and sediments has been found to be a challenging undertaking. Finding an appropriate solution for the disposal of nuclear waste is an important issue for protection of the environment and public health, and it is a prerequisite for the future of nuclear power. The purpose of a deep geological repository for nuclear waste is to provide to future generations, protection against any harmful release of radioactive material, even after the memory of the repository may have been lost, and regardless of the technical knowledge of future generations. The results of a wide variety of investigations on the development of technology for radioactive waste isolation from 19 countries were published in the First Worldwide Review in 1991 (Witherspoon, 1991). The results of investigations from 26 countries were published in the Second Worldwide Review in 1996 (Witherspoon, 1996). The results from 32 countries were summarized in the Third Worldwide Review in 2001 (Witherspoon and Bodvarsson, 2001). The last compilation had results from 24 countries assembled in the Fourth Worldwide Review (WWR) on radioactive waste isolation (Witherspoon and Bodvarsson, 2006). Since publication of the last report in 2006, radioactive waste disposal approaches have continued to evolve, and there have been major developments in a number of national geological disposal programs. Significant experience has been obtained both in preparing and reviewing cases for the operational and long-term safety of proposed and operating repositories. Disposal of radioactive waste is a complex issue, not only because of the nature

  3. From laboratory experiments to a geological disposal vault: calculation of used nuclear fuel dissolution rates

    International Nuclear Information System (INIS)

    Sunder, S.; Shoesmith, D.W.; Kolar, M.; Leneveu, D.M.

    1998-01-01

    Calculation of used nuclear fuel dissolution rates in a geological disposal vault requires a knowledge of the redox conditions in the vault. For redox conditions less oxidizing than those causing UO 2 oxidation to the U 3 O 7 , stage, a thermodynamically-based model is appropriate. For more oxidizing redox conditions a kinetic or an electrochemical model is needed to calculate these rates. The redox conditions in a disposal vault will be affected by the radiolysis of groundwater by the ionizing radiation associated with the fuel. Therefore, we have calculated the alpha-, beta- and gamma-dose rates in water in contact with the reference used fuel in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) as a function of cooling time. Also, we have determined dissolution rates of UO 2 fuel as a function of alpha and gamma dose rates from our electrochemical measurements. These room-temperature rates are used to calculate the dissolution rates of used fuel at 100 o C, the highest temperature expected in a container in the CNFWMP, as a function of time since emplacement. It is shown that beta radiolysis of water will be the main cause of oxidation of used CANDU fuel in a failed container. The use of a kinetic or an electrochemical corrosion model, to calculate fuel dissolution rates, is required for a period of ∼1000 a following emplacement of copper containers in the geologic disposal vault envisaged in the CNFWMP. Beyond this time period a thermodynamically-based model adequately predicts the fuel dissolution rates. The results presented in this paper can be adopted to calculate used fuel dissolution rates for other used UO 2 fuels in other waste management programs. (author)

  4. Horonobe Underground Research Laboratory project. Synthesis of phase 1 investigation 2001-2005, Volume 'geological disposal research'

    International Nuclear Information System (INIS)

    Fujita, Tomoo; Taniguchi, Naoki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Ota, Kunio; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Hama, Katsuhiro; Kunimaru, Takanori; Takeuchi, Ryuji; Tanai, Kenji; Kurikami, Hiroshi; Wakasugi, Keiichiro; Ishii, Eiichi

    2011-03-01

    This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project, of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the project as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)

  5. Horonobe Underground Research Laboratory project synthesis of phase I investigation 2001-2005. Volume 'Geological disposal research'

    International Nuclear Information System (INIS)

    Fujita, Tomoo; Taniguchi, Naoki; Tanai, Kenji; Nishimura, Mayuka; Kobayashi, Yasushi; Hiramoto, Masayuki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Wakasugi, Keiichiro; Nakano, Katsushi; Seo, Toshihiro; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Kurikami, Hiroshi; Kunimaru, Takanori; Ishii, Eiichi; Ota, Kunio; Hama, Katsuhiro; Takeuchi, Ryuji

    2007-03-01

    This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project (HOR), of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the surface-based investigations in HOR as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)

  6. 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

  7. 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

  8. On ocean island geological repository - a second-generation option for disposal of spent fuel and high-level waste

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1993-01-01

    The concept of an ocean subseabed geological high-level waste repository with access via an ocean island is discussed. The technical advantages include, in addition to geologic waste isolation, geographical isolation, near-zero groundwater flow through the disposal site, and near-infinite ocean dilution as a backup in the event of a failure of the repository geological waste isolation system. The institutional advantages may include reduced siting problems and the potential of creating an international waste repository. Establishment of a repository accepting wastes from many countries would allow cost sharing, aid international nonproliferation goals, and ensure proper disposal of spent fuel from developing countries. Major uncertainties that are identified in this concept are the uncertainties in rock conditions at waste disposal depths, costs, and ill-defined institutional issues

  9. 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)

  10. Preliminary conceptual design of a geological disposal system for high-level wastes from the pyroprocessing of PWR spent fuels

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui-Joo, E-mail: hjchoi@kaeri.re.kr [Korea Atomic Energy Research Institute, 1045 Daeduk-Daero, Yuseong, Daejon 305-353 (Korea, Republic of); Lee, Minsoo; Lee, Jong Youl [Korea Atomic Energy Research Institute, 1045 Daeduk-Daero, Yuseong, Daejon 305-353 (Korea, Republic of)

    2011-08-15

    Highlights: > A geological disposal system consists of disposal overpacks, a buffer, and a deposition hole or a disposal tunnel for high-level wastes from a pyroprocessing of PWR spent fuels is proposed. The amount and characteristics of high-level wastes are analyzed based on the material balance of pyroprocessing. > Four kinds of deposition methods, two horizontal and two vertical, are proposed. Thermal design is carried out with ABAQUS program. The spacing between the disposal modules is determined for the peak temperature in buffer not to exceed 100 deg. C. > The effect of the double-layered buffer is compared with the traditional single-layered buffer in terms of disposal density. Also, the effect of cooling time (aging) is illustrated. > All the thermal calculations are represented by comparing the disposal area of PWR spent fuels with the same cooling time. - Abstract: The inventories of spent fuels are linearly dependent on the production of electricity generated by nuclear energy. Pyroprocessing of PWR spent fuels is one of promising technologies which can reduce the volume of spent fuels remarkably. The properties of high-level wastes from the pyroprocessing are totally different from those of spent fuels. A geological disposal system is proposed for the high-level wastes from pyroprocessing of spent fuels. The amount and characteristics of high-level wastes are analyzed based on the material balance of pyroprocessing. Around 665 kg of monazite ceramic wastes are expected from the pyroprocessing of 10 MtU of PWR spent fuels. Decay heat from monazite ceramic wastes is calculated using the ORIGEN-ARP program. Disposal modules consisting of storage cans, overpacks, and a deposition hole or a disposal tunnel are proposed. Four kinds of deposition methods are proposed. Thermal design is carried out with ABAQUS program and geological data obtained from the KAERI Underground Research Tunnel. Through the thermal analysis, the spacing between the disposal modules

  11. Review of the effective approaches for providing the R and D information on the geological disposal of HLW

    International Nuclear Information System (INIS)

    Mitsuhashi, Hiroshi; Okuhara, Hidehiko; Nanjo, Yuki

    2001-03-01

    Japan Nuclear Cycle Development Institute (JNC) had already carried out Research and development (R and D) activities for the Geological Disposal of High-level Radioactive Waste (HLW) in Japan, the information activities in order to gain a public understanding in Japan. At present, however, the information on the geological disposal project including R and D is still unpopular among the public and does not draw so much attention compared to the other current topics. To make a national consensus on the project, the effective public relational activities with the suitable approaches for the various groups/classes among the public should be done. From the viewpoint of gaining the social recognition, having the valuable interviews with the authorities, opinion leaders and other specialists, we reviewed the approaches of the effective information activities to gain the public attention and let them have proper understanding. We also had some group interviews subject to the university students and housewives, who are expected to have no concern with the geological disposal. During these interviews, we had monitored the degree of understanding on the geological disposal and JNC's R and D activities utilizing the conventional materials that JNC had already prepared, such as brochures and video tape recording, and found if the materials were helpful or not, for proper understanding. A questionnaire survey on the internet was done, as one of yardsticks for the effect of the JNC's activities. We studied the degree of understanding of the respondents, and analyzed the effect of the JNC's public relational activities. Based on the another questionnaire survey results at 'Forum on geological disposal', which was held by JNC, we also analyzed the effect of the forum as one of two-way communications tools. Following the above analysis, the effective approaches of the future public relational activities of the Geological disposal was reviewed. (author)

  12. 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.

  13. The solubility of U, Np, Pu, Th and Tc in a geological disposal vault for used nuclear fuel

    International Nuclear Information System (INIS)

    Lemire, R.J.; Garisto, F.

    1989-12-01

    This document describes the solubility model used to calculate the concentrations of uranium, thorium, technetium, neptunium and plutonium in a geological disposal vault for used nuclear fuel. This model is incorporated in the vault model of SYVAC3-CC3 - the third generation of the Systems Variability Analysis Code used to assess the long-term safety of the disposal of Canada's nuclear fuel waste. The data for the solubility model and the sources for these data are also reported

  14. A preliminary study on the suitability of host rocks 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; Park, Byung Yun; Koh, Young Kown

    2000-02-01

    It is expected that the key issues are listed as the disposal concept, reference disposal system and other relevant technical development for the deep geological disposal of HLW in each country. First above all, however, the preferred host rocks should be suggested prior execution of these activities. And, it is desirable to be reviewed and proposed some host rocks representative its country. For the reviewing of host rocks in Korean peninsula, several issues were considered such as the long-term geological stability, fracture system, surface and groundwater system and geochemical characteristics in peninsula. The three rock types such as plutonic rocks, crystalline gneisses and massive volcanic rocks were suggested as the preferred host rocks for the R and D of HLW disposal based on the upper stated information. In the following stages, it is suggested that these preferred host rocks would be made an object of all relevant R and D activities for HLW disposal. And, many references for these geologic medium should be characterized and constructed various technical development for the Korean reference disposal system.

  15. A preliminary study on the suitability of host rocks 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; Park, Byung Yun; Koh, Young Kown

    2000-02-01

    It is expected that the key issues are listed as the disposal concept, reference disposal system and other relevant technical development for the deep geological disposal of HLW in each country. First above all, however, the preferred host rocks should be suggested prior execution of these activities. And, it is desirable to be reviewed and proposed some host rocks representative its country. For the reviewing of host rocks in Korean peninsula, several issues were considered such as the long-term geological stability, fracture system, surface and groundwater system and geochemical characteristics in peninsula. The three rock types such as plutonic rocks, crystalline gneisses and massive volcanic rocks were suggested as the preferred host rocks for the R and D of HLW disposal based on the upper stated information. In the following stages, it is suggested that these preferred host rocks would be made an object of all relevant R and D activities for HLW disposal. And, many references for these geologic medium should be characterized and constructed various technical development for the Korean reference disposal system

  16. CoolRep H22: Synthesis report on R and D results on geological disposal up to 2009

    International Nuclear Information System (INIS)

    Umeki, Hiroyuki; Hioki, Kazumasa; Osawa, Hideaki; Fujita, Tomoo; Shibata, Masahiro; Makino, Hitoshi; Takeuchi, Shinji; Ishimaru, Tsuneari

    2011-02-01

    The Japan Atomic Energy Agency (JAEA) has been performing research and development on geological disposal technology of high level radioactive waste. At the end of fiscal year 2009, the Geological Isolation Research and Development Directorate of JAEA made publicly available the 'CoolRep H22', which is a web-based report that summarizes the R and D results, on its website. This document reports the contents of CoolRep H22. (author)

  17. 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

  18. Current status of regional hydrogeological studies and numerical simulations on geological disposal

    International Nuclear Information System (INIS)

    Nakao, Shinsuke; Kikuchi, Tsuneo; Ishido, Tsuneo

    2004-01-01

    Current status of regional hydrogeological studies on geological disposal including hydrogeological modeling using numerical simulators is reviewed in this report. A regional scale and boundary conditions of numerical models are summarized mainly from the results of the RHS (regional hydrogeological study) project conducted by Japan Nuclear Cycle Development Institute (JNC) in the Tono area. We also refer to the current conceptual modes of hydrology and numerical models of unsaturated zone flow at Yucca Mountain, Nevada, which is the arid site proposed for consideration as the United States' first underground high-level radioactive waste repository. Understanding behavior of a freshwater-saltwater transition zone seems to play a key role in the hydrogeological modeling in a coastal region. Technical features of a numerical simulator as a tool for geothermal reservoir modeling is also briefly described. (author)

  19. 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.

  20. Risk methodology for geologic disposal of radioactive waste: model description and user manual for Pathways model

    International Nuclear Information System (INIS)

    Helton, J.C.; Kaestner, P.C.

    1981-03-01

    A model for the environmental movement and human uptake of radionuclides is presented. This model is designated the Pathways-to-Man Model and was developed as part of a project funded by the Nuclear Regulatory Commission to design a methodology to assess the risk associated with the geologic disposal of high-level radioactive waste. The Pathways-to-Man Model is divided into two submodels. One of these, the Environmental Transport Model, represents the long-term distribution and accumulation of radionuclides in the environment. This model is based on a mixed-cell approach and describes radionuclide movement with a system of linear differential equations. The other, the Transport-to-Man Model, represents the movement of radionuclides from the environment to man. This model is based on concentration ratios. General descriptions of these models are provided in this report. Further, documentation is provided for the computer program which implements the Pathways Model

  1. Paleocorrosion studies in deep sea sediments and the geological disposal of nuclear wastes

    International Nuclear Information System (INIS)

    Fehrenbach, L.; Maurette, M.; Guichard, F.; Havette, A.; Monaco, A.

    1984-01-01

    Uncertainties still surround assessment of the safety of disposal of nuclear wastes incorporated into 'radwaste' matrices. This is mostly due to the long time required for radioactive decay of 237 Np. The present work explores the usefulness of an experimental approach in 'paleocorrosion', which should help in minimizing such uncertainties. In this approach, polished sections of sediments containing high concentrations of natural analogues of radwaste matrices are subjected to element micromapping. Thus it is possible to characterize the long-term interactions of such analogues in their geological repositories, and to identify which generate reaction aureoles and protective and/or unprotective coatings. These analogues include grains incorporated in deep sea sediments (uraninite and quartz from the Oklo uranium ore deposit; volcanic ash particles; magnetic cosmic spherules). The present results indicate that uraninite should be a much more durable radwaste matrix than any type of glass in deep sea sediments. (orig./TWO)

  2. Radioactive waste management: the relation between geological disposal and advanced nuclear technologies

    International Nuclear Information System (INIS)

    Schroder, Jantine

    2013-01-01

    Throughout this paper we aim to scope the most pregnant themes, issues and research questions concerning the relation between geological disposal and advanced nuclear technologies in the broad context of radioactive waste management. Especially from a socio-technical point of view the mutual impacts, divergences and complementarities between both strategies seem to have received limited dedicated examination up until today. Specific attention is paid to the main arguments that seem to underpin both research streams, related to how the issue of radioactive waste is contextualized and which problems and solutions are consequently identified and proposed. Ultimately we aim to encourage scientifically integer communication and constructive dialogue between both fields, to investigate the common possibilities of enhancing radioactive waste management as a whole. (authors)

  3. 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

  4. Geotechnical, geological, and selected radionuclide retention characteristics of the radioactive waste disposal site near the Farallon Islands

    Science.gov (United States)

    Booth, J.S.; Winters, W.J.; Poppe, L.J.; Neiheisel, J.; Dyer, R.S.

    1989-01-01

    A geotechnical and geological investigation of the Farallon Islands low-level radioactive waste (LLW) disposal area was conducted to qualitatively assess the host sediments' relative effectiveness as a barrier to radionuclide migration, to estimate the portion of the barrier that is in contact with the waste packages at the three primary disposal sites, and to provide a basic physical description of the sediments. Box cores recovered from within the general disposal area at depths of 500, 1000, and 1500 m were subcored to provide samples (~30 cm in length) for detailed descriptions, textural and mineralogical analyses, and a suite of geotechnical tests (index property, CRS consolidation, and CIU triaxial compression). -from Authors

  5. Investigations of possibilities to dispose of spent nuclear fuel in Lithuania: a model case. Volume 1, Suitability of Geological Environment in Lithuania for Disposal of Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Motiejunas, S.; Satkunas, J.

    2005-01-01

    This Volume contains an overview of geological structure with respect to its relevance for waste disposal conditions and characteristics of crystalline rocks in Lithuania with respect to its relevance for waste disposal. The most prospective rock types are represented by cratonic (anorogenic) granitoid intrusions that in some places compose rather large massifs. These rocks are the least damaged by tectonic activity. Furthermore, the lithology variations at short distances are only minor that makes exploration much easier. Yet, other rock types (gneisses, mafic intrusions, migmatites) compose someplace only weakly fractured blocks that also may be prospective for repository

  6. ONR Licensing and Regulation of a Geological Disposal Facility in the UK

    International Nuclear Information System (INIS)

    Boydon, Frans; Glazbrook, David

    2014-01-01

    Document available in abstract form only. Full text follows: The UK has substantial quantities of waste which has arisen from operation and decommissioning of legacy nuclear plant. While a disposal route for Low Level Waste (LLW) has been in operation in the UK for many years, there is as yet no such route for Higher Activity Waste. The government invited local communities to express an interest in hosting a Geological Disposal Facility (GDF). However, the Scottish government is opposed to deep disposal and proposes long-term interim storage in Scotland. This paper describes the work underway and current progress in developing a GDF for the UK. In particular it describes the current legal system in the UK that enables nuclear facilities to be licensed and the background underpinning licensing of existing disposal facilities. It identifies changes which will be necessary to legislation to enable a GDF to be licensed and work which it is performing in close co-operation with the Environment Agency which operate a permitting regime for environmental aspects. The Office of Nuclear Regulation (ONR) regulates safety, security and transport associated with nuclear sites. This paper focuses on the regulation of safety and radioactive waste. The UK licensing regime is non-prescriptive and proportionate, allowing for a flexible approach to licensing. The licence is not time-limited but is designed to be used from construction, through commissioning for the lifetime of the facility. Under the Nuclear Installations Act 1965 (as amended) ONR may attach licence conditions: - In the interests of safety; or - with respect to the handling, treatment and disposal of nuclear matter. ONR has developed a suite of 36 Licence conditions, which typically require the operator to made 'adequate arrangements' to ensure safety. These arrangements would involve the use of 'hold points' beyond which the operator must not proceed without ONR's agreement. In determining

  7. Characterization and evaluation of sites for deep geological disposal of radioactive waste in fractured rocks. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    The third Aespoe International Seminar was organised by SKB to assess the state of the art in characterisation and evaluation of sites for deep geological disposal of radioactive waste in fractured rocks. Site characterisation and evaluation are important elements for determining the site suitability and long-term safety of a geological repository for radioactive waste disposal. Characterisation work also provides vital information for the design of the underground facility and the engineered barrier system that will contain the waste. The aim of the seminar was to provide a comprehensive assessment of the current know-how on this topic based on world-wide experience from more than 20 years of characterisation and evaluation work. The seminar, which was held at the Aespoe Hard Rock Laboratory was attended by 72 scientists from 10 different countries. The program was divided into four sessions of which two were run in parallel. A total of 38 oral and 5 poster presentations were given at the seminar. The presentations gave a comprehensive summary of recently completed and current work on site characterisation, modelling and application in performance assessments. The results presented at the seminar generally show that significant progress has been made in this field during the last decade. New characterisation techniques have become available, strategies for site investigations have developed further, and model concepts and codes have reached new levels of refinement. Data obtained from site characterisation have also successfully been applied in several site specific performance assessments. The seminar clearly showed that there is a solid scientific basis for assessing the suitability of sites for actual repositories based on currently available site characterisation technology and modelling capabilities. Separate abstracts have been prepared for 38 of the presentations

  8. Development of the sorption and diffusion database system for safety assessment of geological disposal

    International Nuclear Information System (INIS)

    Tachi, Yukio; Tochigi, Yoshikatsu; Suyama, Tadahiro; Saito, Yoshihiko; Yui, Mikazu; Ochs, Michael

    2009-02-01

    Japan Atomic Energy Agency (JAEA) has been developing databases of sorption and diffusion parameters in buffer material (bentonite) and rock, which are key parameters for safety assessment of the geological disposal. These sorption and diffusion databases (SDB/DDB) have been firstly developed as an important basis for the H12 performance assessment (PA) of high-level radioactive waste disposal in Japan, and have been provided through the Web. JAEA has been and is continuing to improve and update the SDB/DDB in view of potential future data needs, focusing on assuring the desired quality level and testing the usefulness of the existing databases for possible applications to parameter-setting for the deep geological environment. The new web-based sorption and diffusion database system (JAEA-SDB/DDB) has been developed to utilize quality assuring procedure and to allow effective application for parameter setting, by adding the following functions to the existing database; - consistency and linkage between sorption and diffusion database - effective utilization of quality assuring (QA) guideline and categolized QA data - additional function for estimating of parameters and graphing of relation between parameters - counting and summarizing function for effective access to respective data for parameter setting. In the present report, practical examples were illustrated regarding the applicability of the database system to the parameter setting by using additional functions such as QA information and data estimation. This database system is expected to make it possible to obtain quick overview of the available data from the database, and to have suitable access to the respective data for parameter-setting for performance assessment and parameter-deriving for mechanistic modeling in traceable and transparent manner. (author)

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

    International Nuclear Information System (INIS)

    Chen Zhangru

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    Centre d'Etude de l'Energie Nucleaire, Mol

    1987-01-01

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

  11. Preliminary analysis of engineered barrieer performances in geological disposal of high level waste

    International Nuclear Information System (INIS)

    Ohe, Toshiaki; Maki, Yasuo; Tanaka, Hiroshi; Kawanishi, Motoi.

    1988-01-01

    This report represents preliminary results of safety analysis of a engineered barrier system in geological disposal of high level radioactive waste. Three well-known computer codes; ORIGEN 2, TRUMP, and SWIFT were used in the simulation. Main conceptual design of the repository was almost identical to that of SKB in Sweden and NAGRA in Switzerland; the engineered barrier conasists glass solidified waste, steel overpack, and compacted bentonite. Two different underground formations are considered; granite and neogene sedimentary rock, which are typically found in Japan. We first determined the repository configuration, particularly the space between disposal pitts. The ORIGEN 2 was used to estimate heat generation in the waste glass reprocessed at 4 years after removal from PWR. Then, temperature distribution was calculated by the TRUMP. The results of two or three dimensional calculation indicated that the pit interval should be kept more than 5 m in the case of granite formation at 500 m depth, according to the temperature criteria in the bentonite layer ( 90 Sr, 241 Am, 239 Pu, and 237 Np were chosen in one or two dimensional calculations. For both cases of steady release and instanteneous release, the maximum concentration in the pore water at the boundary between bentonite and surrounding rock had the following order; 237 Np> 239 Pu> 90 Sr> 241 Am. Sensitivity analysis showed that the order mainly due to the different adsorption characteristics of the nuclides in bentonite layer. (author)

  12. Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation

    International Nuclear Information System (INIS)

    2008-01-01

    The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

  13. Perspectives for deep geological formation disposal research in France beyond 2006

    International Nuclear Information System (INIS)

    Landais, P.

    2006-01-01

    One finalised aim underlies research conducted on the feasibility of geological disposal: the possibility of having a reversible disposal system available. A model has been drawn up to provide a framework for the analysis and propose possible research content between 2006 and 2015. This period will correspond to the move from the feasibility to a development, optimisation and detailed study phase. It aims at answering any questions raised by reviewers and develops forward the study of a repository. It will also correspond to the consolidation of scientific data, greater understanding of certain mechanisms and an approach of scientific and technical integration. Another goal of the period 2006-2015 would be to collect elements for a decision on the sitting issue through an extended survey. This phase of development includes confirmation of the data acquired during the previous phase and over relatively long periods, optimisation of repository concepts and detailed study of their main components, the production of full-scale mock-ups or simulations to validate the main technological design points and refining of data extrapolation methods. (author)

  14. Extended biosphere dataset for safety assessment of radioactive waste geological disposal

    International Nuclear Information System (INIS)

    Kato, Tomoko; Suzuki, Yuji

    2007-01-01

    JAEA has an on-going programme of research and development relating to the safety assessment of the deep geological disposal systems of high-level radioactive waste (HLW) and transuranic waste (TRU). In the safety assessment of HLW and TRU disposal systems, biosphere assessment is necessary to estimate future radiological impacts on human beings (e.g. radiation dose). In order to estimate radiation dose, consideration needs to be given to the biosphere into which future releases of radionuclides might occur and to the associated future human behaviour. The data of some biosphere parameters needed to be updated by appropriate data sources for generic and site-specific biosphere assessment to improve reliability for the biosphere assessment, because some data published in the 1980's or the early 90's were found to be inappropriate for the recent biosphere assessment. Therefore, data of the significant parameters (especially for element-dependent) were set up on the basis of recent information, to update the generic biosphere dataset. (author)

  15. Development of probabilistic assessment methodology for geologic disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Kimura, H.; Takahashi, T.

    1998-01-01

    The probabilistic assessment methodology is essential to evaluate uncertainties of long-term radiological consequences associated with geologic disposal of radioactive wastes. We have developed a probabilistic assessment methodology to estimate the influences of parameter uncertainties/variabilities. An exposure scenario considered here is based on a groundwater migration scenario. A computer code system GSRW-PSA thus developed is based on a non site-specific model, and consists of a set of sub modules for sampling of model parameters, calculating the release of radionuclides from engineered barriers, calculating the transport of radionuclides through the geosphere, calculating radiation exposures of the public, and calculating the statistical values relating the uncertainties and sensitivities. The results of uncertainty analyses for α-nuclides quantitatively indicate that natural uranium ( 238 U) concentration is suitable for an alternative safety indicator of long-lived radioactive waste disposal, because the estimated range of individual dose equivalent due to 238 U decay chain is narrower that that due to other decay chain ( 237 Np decay chain). It is internationally necessary to have detailed discussion on the PDF of model parameters and the PSA methodology to evaluated the uncertainties due to conceptual models and scenarios. (author)

  16. Advances in the self-burial concept for deep geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Logan, S.E.

    1996-01-01

    The self-burial concept for deep geological disposal of high-level radioactive waste seeks to utilize the radioactive decay heat emitted by the wastes to melt rock and allow descent by gravity into crystalline rock for isolation. Logan developed the governing equations for the self-disposal process in a paper published in 1973 and 1974 showing that moderate waste concentrations in capsules 1 to 2 m in diameter could descend through granite or basalt to considerable depths, in some cases grater than 10 km. Safety considerations related to filling, handling, and initial cooling of such large capsules prior to release, plus the severe container material environment, has prevented use of the concept. Byalko in Russia recently proposed using a sulfur-filled borehole as a conduit for conveying small capsules down to an accumulation zone at a safe depth of several kilometers. This advance in the self-burial concept overcomes previous problems with self-burial. First, capsules of 0.3 m or less in diameter are relatively simple to fill and handle. Second, investigations indicate that once emplaced at an initial accumulation depth, rock-melting can proceed without an enveloping waste container

  17. Development of the geologic waste disposal programme in the United States of America

    International Nuclear Information System (INIS)

    Coffman, F.E.; Ballard, W.W.; Carbiener, W.A.

    1983-01-01

    Although alternative concepts are being studied as future options, over at least the next few decades the United States of America is committed to the disposal of commercially generated high-level and transuranic nuclear waste (HLW and TRU) in mined geologic repositories. A 10,000-year minimum isolation period is sought. Responsibility for the management and disposal of United States nuclear waste, in accordance with standards and regulations established, respectively, by the Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC), resides with the Department of Energy (DOE). The DOE National Waste Terminal Storage (NWTS) Program has been implemented to provide the facilities and develop the requisite technology for the disposal of HLW and TRU. The NWTS Program is highly structured, adequately funded, and realistically scheduled. The timely realization of its objectives is basic to the furtherance of the new national energy policy being defined by President Reagan and the United States Congress. The first NWTS repository is scheduled to be operational as early as 1998. The host-rock formation, selected on the basis of the results of at-depth investigations via exploratory shafts to be sunk in 1983-1985 at three potential sites previously extensively characterized by surface techniques, will be either basalt, volcanic tuff, or domed or bedded salt. Selection of one site in these formations will not necessarily disqualify others. Also, screening studies of granitic formations in the United States for the siting of later, regionally located repositories are currently being conducted. Each NWTS repository will be licensed by the NRC. The first application for a construction authorization will probably be submitted in 1988. The application will be submitted for a site to be selected in 1987

  18. 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)

  19. Feasibility studies for alpha waste disposal on geological formations in France

    International Nuclear Information System (INIS)

    Jaouen, C.; Boulanger, A.

    1985-01-01

    Since 1977, SGN has been involved in many feasibility studies and consultant works in the fields of HLW storages. Starting as nuclear consultant company in the KBS review of the long term storage of HLW, SGN and Geostock were entrusted in 1978 by the EEC for the basic design and evaluation of the deep storage into granite rock of HLW, followed by a participation in the thermal sensitivity study of such a storage. The cooperation with Geostock was first extended in 1981 to a preliminary study of HLW storage conditions in granite for a Japanese company, and then in France for several feasibility studies of HLW and TRU waste geological disposal. Three kinds of scenarios have been forecasted and evaluated in the case of vitrified HLW storage, allowing the thermal power to be decreased and the whole management scheme to be optimized. More recently, SGN participation to French engineering studies has been extended by ANDRA to the TRU waste repository evaluation. All these works for French authorities have been performed in a close connection with several specialized departments in the CEA group, and with the help of geological specialists, under the leadership of ANDRA [fr

  20. Long-term risk assessment of radioactive waste disposal in geological formations

    International Nuclear Information System (INIS)

    Girardi, F.; Bertozzi, G.; D'Alessandro, M.

    1978-01-01

    Methods for long-term safety analysis of waste from nuclear power production in the European Community are under study at the Joint Research Centre (JRC) at Ispra, Italy. Aim of the work is to develop a suitable methodology for long-term risk assessment. The methodology under study is based on the assessment of the quantitative value of a system of barriers which may be interposed between waste and man. The barriers considered are: a) quality of the segregation afforded by the geological formation, b) chemical and physical stability of conditioned waste, c) interaction with geological environments (subsoil retention), d) distribution in the biosphere. The methodology is presently being applied to idealized test cases based on the following assumptions: waste are generated during 30 years of operations in a nuclear park (reprocessing + refabrication plant) capable of treating 1000 ton/yr of LWR fuel. High activity waste is conditioned as borosilicate glass (HAW) while low- and medium-level wastes are bituminized (BIP). All waste is disposed off into a salt formation. Transport to the biosphere, following the containment failure occurs by groundwater, with no delay due to retention on adsorbing media. Distribution into the biosphere occurs according to the terrestrial model indicated. Under these assumptions, information was drawn concerning environmental contamination, its levels, contributing elements and pathways to man

  1. 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.)

  2. Feasibility studies for alpha waste disposal on geological formations in France

    International Nuclear Information System (INIS)

    Jaouen, C.; Boulanger, A.

    1986-01-01

    Since 1977, SGN has been involved in many feasibility studies and consultant works in the fields of HLW storages. Starting as nuclear consultant company in the KBS review of the long term storage of HLW, SGN and GEOSTOCK were entrusted in 1978 by the EEC for the basic design and evaluation of the deep storage into granite rock of HLW, followed by a participation in the thermal sensitivity study of such a storage. The cooperation with GEOSTOCK was first extended in 1981 to a preliminary study of HLW storage conditions in granite for a Japanese company, and then in France for several feasibility studies of HLW and TRU waste geological disposal. Three kinds of scenarios have been forecasted and evaluated in the case of vitrified HLW storage, allowing the thermal power to be decreased and the whole management scheme to be optimized. More recently, SGN participation to French engineering studies has been extended by ANDRA to the TRU waste repository evaluation. All these works for French authorities have been performed in a close connection with several specialized departments in the CEA group, and with the help of geological specialists, under the leadership of ANDRA [fr

  3. Materials interactions relating to long-term geologic disposal of nuclear waste glass

    International Nuclear Information System (INIS)

    Bibler, N.E.; Jantzen, C.M.

    1987-01-01

    In the geologic disposal of nuclear waste glass, the glass will eventually interact with groundwater in the repository system. Interactions can also occur between the glass and other waste package materials that are present. These include the steel canister that holds the glass, the metal overpack over the canister, backfill materials that may be used, and the repository host rock. This review paper systematizes the additional interactions that materials in the waste package will impose on the borosilicate glass waste form-groundwater interactions. The repository geologies reviewed are tuff, salt, basalt, and granite. The interactions emphasized are those appropriate to conditions expected after repository closure, e.g. oxic vs anoxic conditions. Whenever possible, the effect of radiation from the waste form on the interactions is examined. The interactions are evaluated based on their effect on the release and speciation of various elements including radionuclides from the glass. It is noted when further tests of repository interactions are needed before long-term predictions can be made. 63 references, 1 table

  4. 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.

  5. Performance assessment of geological isolation systems for radioactive waste. Disposal in clay formations

    International Nuclear Information System (INIS)

    Marivoet, J.; Bonne, A.

    1988-01-01

    In the framework of the PAGIS project of the CEC Research Programme on radioactive waste, performance assessment studies have been undertaken on the geological disposal of vitrified high-level waste in clay layers at a reference site at Mol (B) and a variant site at Harwell (UK). The calculations performed for the reference site shown that most radionuclides decay to negligible levels within the first meters of the clay barrier. The maximum dose rates arising from the geological disposal of HLW, as evaluated by the deterministic approach are about 10 -11 Sv/y for river pathways. If the sinking of a water well into the 150 m deep aquifer layer in the vicinity of the repository is considered together with a climatic change, the maximum calculated dose rate rises to a value of 3.10 -7 Sv/y. The calculated maxima arise between 1 million and 15 million years after disposal. The maximum dose rates evaluated by stochastic calculations are about one order of magnitude higher due to the considerable uncertainties in the model parameters. In the case of the Boom clay the estimated consequences of a fault scenario are of the same order of magnitude as the results obtained for the normal evolution scenario. The maximum risk is estimated from stochastic calculations to be about 4.10 -8 per year. For the variant site the case of the normal evolution scenario has been evaluated. The maximum dose rates calculated deterministically are about 1.10 -6 Sv/y for river pathways and 6.10 -5 Sv/y for a water well pathways; these doses would occur after about 1 million years. This document is one of a set of 5 reports covering a relevant project of the European Community on a nuclear safety subject having very wide interest. The five volumes are: the summary (EUR 11775-EN), the clay (EUR 11776-EN), the granite (EUR 11777-FR), the salt (EUR 11778-EN) and the sub-seabed (EUR 11779-EN)

  6. 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)

  7. Geological site selection studies for the final disposal of spent nuclear fuel in Finland

    International Nuclear Information System (INIS)

    Salmi, M.; Vuorela, P.; Kuivamaeki, A.

    1985-10-01

    In the work of selecting at the areas, heed has been taken of international geological recommendations, which have been adapted to local conditions prevailing in this country. At the present stage, the studies are largely based on the available information about the bedrock of Finland, as contained in, for example, geological maps, various geophysical maps covering the country as a whole and the maps of ore deposits and indications as well as of groundwater areas. The regional investigations of the structure of the Finnish bedrock has taken as its point of departure the study of satellite photos. These pictures best show the mosaiclike block structure of the Finnish bedrock, where the fracture zones surrounding the blocks are involved in the movements of the bedrock resulting mainly from land uplift. From the interpretation of satellite photos, attention has switched over to the interpretation of large-scale maps and stereoscopic aerial photographs. The investigation areas selected by the interpretation of aerial photos have also been studied tentatively on the ground to obtain a more accurate comparative estimation of the different localities. Of the areas chosen for study, the majority consist of granites, which best meet the geological site selection recommendations. The investigation areas have been classified into four categories according to how well they are suited to further study. One important criterion in the classification has been the amount of information obtainable from the bedrock. The areas included in the first category have well exposed and solid bedrock. The areas chosen for inclusion in the second category contain fewer outcrops and are not so easy to study with respect to the structure of the bedrock. The areas included in the third category are generally blanketed under surficial deposits with the result that obtaining reliable information about the bedrock calls for further investigation. The fourth category represents areas where features

  8. Appendix Q: siting considerations for submarine geologic disposal of nuclear waste

    International Nuclear Information System (INIS)

    Hollister, C.D.; Corliss, B.H.

    1981-01-01

    Site suitability characteristics of submarine geological formations for the disposal of radioactive wastes include the distribution coefficient of the host medium, permeability, viscoelastic nature of the sediments, influence of organic material on remobilization, and effects of thermal stress. The submarine geological formation that appears to best satisfy these criteria is abyssal red clay. Regions in the ocean that have coarse grained deposits, high or variable thermal conductivity, high organic carbon content, and sediment thickness of less than 50 m are not being considered at this time. The optimum geological environment should be tranquil and have environmental predictability over a minimum of 10 5 years. A paleoenvironmental model of Cenozoic sedimentation in the central North Pacific has been constructed from sedimentological, geotechnical and stratigraphic data derived from a single giant piston core collected in the central North Pacific (GPC-3: 30 0 N, 157 0 W; 5705 m). This core represents a record of nearly continuous sedimentation for nearly 70 million years. The core was taken from a region of abyssal hill topography located beneath the present-day carbonate compensation depth. It contains 24.5 meters of undisturbed sediment composed of oxidized brown clay with altered ash layers. Paleomagnetic stratigraphy for the upper 4.5 meters indicates sedimentation rates are 2.5 mm/1000 years for the last 2 m.y. and 1.1 mm/1000 years before that to 2.4 Ma. Ichthyolith stratigraphy shows sedimentation rates of 0.2 to 0.3 mm/1000 years from 65 to 5 Ma. The observed sedimentological variations can be explained in terms of present sedimentation patterns in the central North Pacific and by the NNW motion of the Pacific plate during the Cenozoic

  9. Towards the licensing of the Geological Disposal: Illustration of the 2009-2010 intermediate milestone

    International Nuclear Information System (INIS)

    Boissier, Fabrice; Leverd, Pascal C.; Voinis, Sylvie; Tichauer, Michael

    2014-01-01

    France has a legal and institutional framework for the management of radioactive materials and waste. On June 28, 2006, the Planning Act No. 2006-739 of materials and radioactive waste management was enacted. This French Act mandates Andra (the National Radioactive Waste Management Agency) to conduct studies and research required for the siting and design of a deep disposal facility for high or medium-and long-lived (ILW-LL-HA) radioactive waste in a geological formation, in view of submitting a request for authorization to create such a repository to be examined in 2015. According to French regulations, a creation decree will authorize both the construction of the facility and the nuclear operations to be performed. The commissioning of the repository needs then to be authorized by the Nuclear Safety Authority (ASN) and at the due date of 2025, construction and equipment work shall be carried out concurrently with nuclear operations in the previously commissioned portions. In order to get all the authorizations, Andra will face a number of other external steps including the process of reviewing and evaluating the safety case by the regulatory authority and his technical safety organization (TSO), the Institute of Radioprotection and Nuclear Safety (IRSN). This step by step decision process involves the regulatory authority ASN, IRSN, at some stage the French standing committee in charge of facilities related to nuclear waste management 'GPD', and Andra. The Decree No. 2008-357 of 16 April 2008 made under that Act, sets out interim milestones before 2015, among which the delivery by Andra to the Ministers for Energy, Research and Environment by the end of 2009 of a record to take stock. That record included a share of studies on the design, the safety and the reversibility options, as well as the waste inventory to be disposed. In that frame, Andra sent to the ASN the so-called 'Dossier 2009'. That intermediate stage aimed at helping in building

  10. Impacts on non-human biota from a generic geological disposal facility for radioactive waste: some key assessment issues.

    Science.gov (United States)

    Robinson, C A; Smith, K L; Norris, S

    2010-06-01

    This paper provides an overview of key issues associated with the application of currently available biota dose assessment methods to consideration of potential environmental impacts from geological disposal facilities. It explores philosophical, methodological and practical assessment issues and reviews the implications of test assessment results in the context of recent and on-going challenges and debates.

  11. Impacts on non-human biota from a generic geological disposal facility for radioactive waste: some key assessment issues

    International Nuclear Information System (INIS)

    Robinson, C A; Smith, K L; Norris, S

    2010-01-01

    This paper provides an overview of key issues associated with the application of currently available biota dose assessment methods to consideration of potential environmental impacts from geological disposal facilities. It explores philosophical, methodological and practical assessment issues and reviews the implications of test assessment results in the context of recent and on-going challenges and debates.

  12. Development of the JNC geological disposal technical information integration system subjected for repository design and safety assessment

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Ito, Takashi; Kobayashi, Shigeki; Neyama, Atsushi

    2004-02-01

    On this work, system manufacture about disposal technology and safety assessment field was performed towards construction of the JNC Geological Disposal Technical Information Integration System which systematized three fields of technical information acquired in investigation (site characteristic investigation) of geology environmental conditions, disposal technology (design of deep repository), and performance/safety assessment. The technical information database managed focusing on the technical information concerning individual research of an examination, analysis, etc. and the parameter set database managed focusing on the set up data set used in case of comprehensive evaluation are examined. In order to support and promote share and use of the technical information registered and managed by the database, utility functions, such as a technical information registration function, technical information search/browse function, analysis support function, and visualization function, are considered, and the system realized in these functions is built. The built system is installed in the server of JNC, and the functional check examination is carried out. (author)

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

    International Nuclear Information System (INIS)

    Xu Guoqing

    2004-01-01

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

  14. Study of an applicability of technologies developed in the conventional industries from the view point of developing the geological disposal system

    International Nuclear Information System (INIS)

    Ushio, Kazuhiro; Ando, Yasumasa; Kubota, Kazuo; Sokejima, Susumu

    1999-02-01

    The geological disposal study of HLW (High Level Wastes) is being developed in Japan. Especially, JNC has played the central role to proceed this project, while in the industries, from the viewpoint of the environmental measures, various technologies and materials have been developed. Some of them might be applied into the geological disposal. The purpose of this study is to investigate such technologies and their applicability to the geological disposal system. Firstly, the environmental technologies used for the repository of industrial wastes were studied. The concepts of management and the regulations for the repository are summarized, and compared with the current geological disposal concept. Secondly, concerning structural and durable materials, their properties and usage were overviewed and their applicability to the current geological disposal concept was studied. (J.P.N.)

  15. Study of an optimization approach for a disposal tunnel layout, taking into account the geological environment with spatially heterogeneous characteristics

    International Nuclear Information System (INIS)

    Suyama, Yasuhiro; Toida, Masaru; Yanagizawa, Koichi

    2009-01-01

    The geological environment has spatially heterogeneous characteristics with varied host rock types, fractures and so on. In this case the generic disposal tunnel layout, which has been designed by JNC, is not the most suitable for HLW disposal in Japan. The existence of spatially heterogeneous characteristics means that in the repository region there exist sub-regions that are more favourable from the perspective of long-term safety and ones that are less favourable. In order that the spatially heterogeneous environment itself may be utilized most effectively as a natural barrier system, an alternative design of disposal tunnel layout is required. Focusing on the geological environment with spatially heterogeneous characteristics, the authors have developed an alternative design of disposal tunnel layout. The alternative design adopts an optimization approach using a variable disposal tunnel layout. The optimization approach minimizes the number of locations where major water-conducting fractures are intersected, and maximizes the number of emplacement locations for waste packages. This paper will outline the variable disposal tunnel layout and its applicability.

  16. Conceptual design and cost inputs associated with co-disposal of the spent fuel and long lived radioactive wastes in the deep geologic disposal facility

    International Nuclear Information System (INIS)

    Fako, R.; Sociu, F.; Nicolae, R.; Barariu, G

    2013-01-01

    The paper aims to be an integrated approach for the containment and isolation of spent fuel and / or long lived radioactive wastes in a Deep Geologic Repository in Romania. Several scenarios could be defined for the management of spent fuel and long lived radioactive waste in Romania considering many specific constraints in Romania (political, geological, economic, demographic, etc.). This paper intends to be an upgrade of several Research, Development and Demonstration (RD&D) works performed by SITON specialists on this subject, taking into account also the conclusions of the Workshop ôCost estimation on spent nuclear fuel disposal in Romaniaö organized by IAEA in cooperation with ANDR at the beginning of this year in Romania.This paper is, also, addressed to decision makers with target on to adopt the best strategy for construction of Deep Geologic Repository in Romania. (authors)

  17. Safety regulation of geological disposal of radioactive waste: progress since Cordoba and remaining challenges

    International Nuclear Information System (INIS)

    Duncan, A.; Pescatore, C.

    2010-01-01

    Claudio Pescatore, Deputy Division Head (NEA) presented a paper, the purpose of which was to recall where we stood at the time of the Cordoba Workshop (1997) on the regulation of disposal of long-lived radioactive waste, to review developments since then, to present the key existing issues, and reflect on the remaining challenges and possible responses. The overview study on progress in regulation for geological disposal since the Cordoba workshop [NEA/RWMC/RF(2008)6], provides a good list of references regarding the first two issues. The presentation of the existing issues takes advantage of the synthesis of the responses to a questionnaire completed by the regulatory organisations in preparation for this workshop. It warns regulators and implementers that international work to date seems to have created an expectation in the mind of the public and in some organisations that nothing less than a guarantee by the regulator is needed of maintaining current levels of protection of both individuals and populations practically forever, regardless of the impracticality of this. This expectation needs to be replaced with a carefully and clearly explained understanding of the choices involved in dealing with long-lived radioactive waste against a background of our responsibilities to both current and future generations and our practical capacity to deliver them. Concerning the current major challenges faced in regulation, the paper comes back to the issue of the 'guarantee' by the regulator and it observes that there is no doubt that there is a willingness to do the best to comply with the principle of protection and that we are broadly convinced that current concepts for geological disposal, supported by multiple lines of reasoning and application of best available techniques (BAT) will meet that principle. However, we do not have the capacity to prove or guarantee this, nor do we believe that it is possible in practice. Although we are advised that it is neither

  18. Drilling of deep boreholes and associated geological investigations. Final disposal of spent fuel

    International Nuclear Information System (INIS)

    Anttila, P.

    1983-12-01

    Teollisuuden Voima Oy (Industrial Power Company Ltd.) will take precautions for the final disposal of spent fuel in the Finnish bedrock. The first stage of the site selection studies includes drilling of a deep borehole down to approximately 1000 metres in the winter of 1984. The choice of drilling method and equipment depends on the geological circumstances and the target of the investigation. The most common drilling methods used with the investigations of nuclear waste disposal are diamond core drilling and percussion drilling. The Precambrian bedrock outcropping in Finland exists also in Sweden and Canada, where deep boreholes have been done down to more than 1000 metres using diamond core drilling. This method can be also used in Finland and equipment for the drilling are available. One of the main targets of the investigation is to clarify the true strike and dip of fractures and other discontinuities. The methods used abroad are taking of oriented cores, borehole television survey and geophysical measurements. TV-survey and geophysical methods seem to be most favourable in deep boreholes. Also the accurate position (inclination, bearing) of the borehole is essential to know and many techniques are used for measuring of it. Investigations performed on the core samples include core logging and laboratory tests. For the core logging there is no uniform practice concerning the nuclear waste investigations. Different counries use their own classifications. All of these, however, are based on the petrography and fracture properties of the rock samples. Laboratory tests (petrographical and rock mechanical tests) are generally performed according to the recommendations of international standards. The large volumes of data obtained during investigations require computer techniques which allow more comprehensive collection, storage and processing of data. This kind of systems are already used in Sweden and Canada, for instance, and they could be utilize in Finland

  19. 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

  20. Potential scenarios for broadening stakeholder involvement in the implementing geological disposal technology platform

    Energy Technology Data Exchange (ETDEWEB)

    Martell, Meritxell [Merience Strategic Thinking, Barcelona (Spain); Bergmans, Anne [University of Antwerp, Antwerp (Belgium)

    2013-07-01

    This paper analyses the potential for the involvement of different types of stakeholders in the Implementing Geological Disposal Technology Platform (IGD-TP). This analysis was conducted as part of the InSOTEC project, a three-year (2011- 2014) collaborative research project funded under the 7. Euratom Framework Programme (Grant Agreement nr. 269906). In our analysis, we consider the extent to which the IGDTP's practice as regards to stakeholder involvement matches its discourse, and what potential for improvement exists given its structural organisation as a European Technology Platform (ETPs). Technology Platforms (TPs) can be understood as knowledge networks, deliberately set up to influence (research) policy in a specific domain. We therefore use knowledge networks as a conceptual approach and look at the IGD-TP as a complex network which includes actors, knowledge and practices across different countries, focusing on a very specific topic (i.e. implementing geological disposal). We compare the way different stakeholders are involved in the IGD-TP to the practice of other ETPs, and explore how the IGD-TP is viewed by its members and by outsiders to the platform Applying Callon's framework of knowledge co-production (1999) we come to define different degrees of interaction between science, society and policy in view of defining research and development (R and D) priorities [1]. Subsequently we describe how these interactions could be conceptualised and interpreted for the IGD-TP. The current approach of the IGDTP can be mainly understood as classical model involving mainly expert stakeholders and scientists. Where there seems to be a good representation among IGD-TP members of industry, research institutes, and some members of the academic community this is not the case for other types of stakeholders, such as public authorities or civil society. At this stage, the overall approach of the IGD-TP would seem to restrict the scope of stakeholder

  1. Potential scenarios for broadening stakeholder involvement in the implementing geological disposal technology platform

    International Nuclear Information System (INIS)

    Martell, Meritxell; Bergmans, Anne

    2013-01-01

    This paper analyses the potential for the involvement of different types of stakeholders in the Implementing Geological Disposal Technology Platform (IGD-TP). This analysis was conducted as part of the InSOTEC project, a three-year (2011- 2014) collaborative research project funded under the 7. Euratom Framework Programme (Grant Agreement nr. 269906). In our analysis, we consider the extent to which the IGDTP's practice as regards to stakeholder involvement matches its discourse, and what potential for improvement exists given its structural organisation as a European Technology Platform (ETPs). Technology Platforms (TPs) can be understood as knowledge networks, deliberately set up to influence (research) policy in a specific domain. We therefore use knowledge networks as a conceptual approach and look at the IGD-TP as a complex network which includes actors, knowledge and practices across different countries, focusing on a very specific topic (i.e. implementing geological disposal). We compare the way different stakeholders are involved in the IGD-TP to the practice of other ETPs, and explore how the IGD-TP is viewed by its members and by outsiders to the platform Applying Callon's framework of knowledge co-production (1999) we come to define different degrees of interaction between science, society and policy in view of defining research and development (R and D) priorities [1]. Subsequently we describe how these interactions could be conceptualised and interpreted for the IGD-TP. The current approach of the IGDTP can be mainly understood as classical model involving mainly expert stakeholders and scientists. Where there seems to be a good representation among IGD-TP members of industry, research institutes, and some members of the academic community this is not the case for other types of stakeholders, such as public authorities or civil society. At this stage, the overall approach of the IGD-TP would seem to restrict the scope of stakeholder

  2. Microorganisms in potential host rocks for geological disposal of nuclear waste and their interactions with radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Cherkouk, A.; Liebe, M.; Luetke, L.; Moll, H.; Stumpf, T. [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Inst. of Resource Ecology

    2015-07-01

    The long-term safety of nuclear waste in a deep geological repository is an important issue in our society. Microorganisms indigenous to potential host rocks are able to influence the oxidation state, speciation and therefore the mobility of radionuclides as well as gas generation or canister corrosion. Therefore, for the safety assessment of such a repository it is necessary to know which microorganisms are present in the potential host rocks (e.g. clay, salt) and if these microorganisms can influence the performance of a repository. Microbial diversity in potential host rocks for geological disposal of nuclear waste was analyzed by culture-independent molecular biological methods (e.g. 16S rRNA gene retrieval) as well as enrichment and isolation of indigenous microbes. Among other isolates, a Paenibacillus strain, as a representative of Firmicutes, was recovered in R2A media under anaerobic conditions from Opalinus clay from the Mont Terri in Switzerland. Accumulation experiments and potentiometric titrations showed a strong interaction of Paenibacillus sp. cells with U(VI) within a broad pH range (3-7). Additionally, the interactions of the halophilic archaeal strain Halobacterium noricense DSM 15987, a salt rock representative reference strain, with U(VI) at high ionic strength was investigated. After 48 h the cells were still alive at uranium concentrations up to 60 μM, which demonstrates that Halobacterium noricense can tolerate uranium concentrations up to this level. The formed uranium sorption species were examined with time-resolved laser-induced fluorescence spectroscopy (TRLFS). The results about the microbial communities present in potential host rocks for nuclear waste repositories and their interactions with radionuclides contribute to the safety assessment of a prospective nuclear waste repository.

  3. Microorganisms in potential host rocks for geological disposal of nuclear waste and their interactions with radionuclides

    International Nuclear Information System (INIS)

    Cherkouk, A.; Liebe, M.; Luetke, L.; Moll, H.; Stumpf, T.

    2015-01-01

    The long-term safety of nuclear waste in a deep geological repository is an important issue in our society. Microorganisms indigenous to potential host rocks are able to influence the oxidation state, speciation and therefore the mobility of radionuclides as well as gas generation or canister corrosion. Therefore, for the safety assessment of such a repository it is necessary to know which microorganisms are present in the potential host rocks (e.g. clay, salt) and if these microorganisms can influence the performance of a repository. Microbial diversity in potential host rocks for geological disposal of nuclear waste was analyzed by culture-independent molecular biological methods (e.g. 16S rRNA gene retrieval) as well as enrichment and isolation of indigenous microbes. Among other isolates, a Paenibacillus strain, as a representative of Firmicutes, was recovered in R2A media under anaerobic conditions from Opalinus clay from the Mont Terri in Switzerland. Accumulation experiments and potentiometric titrations showed a strong interaction of Paenibacillus sp. cells with U(VI) within a broad pH range (3-7). Additionally, the interactions of the halophilic archaeal strain Halobacterium noricense DSM 15987, a salt rock representative reference strain, with U(VI) at high ionic strength was investigated. After 48 h the cells were still alive at uranium concentrations up to 60 μM, which demonstrates that Halobacterium noricense can tolerate uranium concentrations up to this level. The formed uranium sorption species were examined with time-resolved laser-induced fluorescence spectroscopy (TRLFS). The results about the microbial communities present in potential host rocks for nuclear waste repositories and their interactions with radionuclides contribute to the safety assessment of a prospective nuclear waste repository.

  4. Characterization of long-term geological changes for final disposal of spent fuel in Finland

    International Nuclear Information System (INIS)

    Vuorela, P.; Blomqvist, R.; Aikaes, T.

    1996-01-01

    The bedrock of Finland is very old and major crustal deformation processes ceased long ago. At present continuous slow processes prevail and geological changes taking place today are very difficult to observe. Anticipated future geological changes are dominated by the renewed development of the continental ice sheet in northern Europe. The present climate will deteriorate to a state amenable to glacier formation. Continuous processes such as groundwater flow and interrelated hydrogeochemical phenomena will be influenced by changes in the climate as well as by developing permafrost. The crust itself will be loaded by the weight of the ice sheet, and will will warp down. The final disposal programme has been devised with even more exceptional future changes in mind. The process of site identification in the site selection research programme has been developed to consider the eventuality of the future bedrock movements. Analysis of bedrock geometry and block patterns, together with related fracture zones assists in selecting a repository site where the risks of accumulation of large stresses, and their subsequent release as shear movements, can be minimized. By studying the prevailing conditions and tracing the record of earlier events an understanding of the relevant processes in general is developed. Paleo-hydrogeology is one of the areas which can provide information relating to 'why the conditions at the site today are as they are'. Although it is not possible to predict the future behavior of a site in a detailed manner, it is possible to constrain the scenarios needed in the safety assessment by establishing and documenting real events that have sometimes occurred, and that will most probably be repeated. (authors). 31 refs., 8 figs

  5. 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)

  6. A simple analysis of potential radiological exposure from geological disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Amiro, B.D.; Dormuth, K.W.

    1996-02-01

    AECL has submitted an environmental impact statement (EIS) describing its proposal for geological disposal of Canada's nuclear fuel waste. The EIS presents a detailed analysis of potential radiation exposure of an individual of a critical group of people in a hypothetical case. In this report, we provide a simpler analysis of potential exposure in the hope that the inherent safety of the disposal will be more readily evident from the analysis. A key to the simplification is the elimination from the analysis of the complex transport processes through disposal vault sealing materials and the geosphere. We also eliminate the relatively complex function describing the failure of the thin-walled titanium containers in the case study presented in the EIS. We therefore conceptually replace the thin-walled titanium containers with thicker-walled copper containers, are expected to remain intact much longer than 10,000 a, the period for which a quantitative estimate of individual exposure is made. However, about 1 in 5000 containers could have small defects that were undetected during manufacture. Our analysis applies only to the case of an undisrupted vault. We assume that the vault and geosphere barriers remain intact and prevent immobile radionuclides from reaching the biosphere. However, we also assume that the three most important mobile radionuclides can escape through an undected manufacturing defect in the container wall, and that the flux of these radionuclides is diluted by well water being used by people. We have focused on 129 I, 36 Cl and 14 C, because these nuclides are found to be the dominant source of exposure in more complex analyses. If a single container released radionuclides to well water, we estimate dose rates of about 1 μSv.a -1 from drinking water and 29 μSv.a -1 , which the Atomic Eenrgy Control Board has adopted as a de minimis dose rate, i.e., a dose rate so small as to not warrant institutional control. We believe that the dose rates are

  7. Preliminary analysis on the disposal of high-level radioactive wastes in geological formations of Sao Paulo state, Brazil

    International Nuclear Information System (INIS)

    Mattos, Luis Antonio Terribile de

    1981-01-01

    Several studies show that deep geological formations are the most promising solution - technical and economical - for the safe disposal of the high-level radioactive wastes produced by the nuclear industry. In order to obtain the necessary information to assess on the use of geological sites in Brazil - for the disposal of high-level radioactive waste generated by the brazilian nuclear industry - a careful survey on the basalt and granite rocks of Sao Paulo State was made. The data obtained were evaluated according to guidelines established by the International Atomic Energy Agency. The favourable and unfavourable characteristics of the basalts, granites and their respective occurrence areas in the Sao Paulo state territory - as potential waste disposal sites - were analysed. This preliminary and regional characterization is not a conclusive study whether these two rocks types are definitively the most suitable geological formations for use as nuclear waste repository or not. It is the subsidy for a more detailed analysis. Other factors such as social, political and economical aspects, ecological effects, engineering geology, heat generation rate of the waste, type of radiation emitted and corrosive nature of the waste must also be taken into account. (author)

  8. Geological disposal of nuclear waste: II. From laboratory data to the safety analysis – Addressing societal concerns

    International Nuclear Information System (INIS)

    Grambow, Bernd; Bretesché, Sophie

    2014-01-01

    Highlights: • Models for repository safety can only partly be validated. • Long term risks need to be translated in the context of societal temporalities. • Social sciences need to be more strongly involved into safety assessment. - Abstract: After more than 30 years of international research and development, there is a broad technical consensus that geologic disposal of highly-radioactive waste will provide for the safety of humankind and the environment, now, and far into the future. Safety analyses have demonstrated that the risk, as measured by exposure to radiation, will be of little consequence. Still, there is not yet an operating geologic repository for highly-radioactive waste, and there remains substantial public concern about the long-term safety of geologic disposal. In these two linked papers, we argue for a stronger connection between the scientific data (paper I, Grambow et al., 2014) and the safety analysis, particularly in the context of societal expectations (paper II). In this paper (II), we assess the meaning of the technical results and derived models (paper I) for the determination of the long-term safety of a repository. We consider issues of model validity and their credibility in the context of a much broader historical, epistemological and societal context. Safety analysis is treated in its social and temporal dimensions. This perspective provides new insights into the societal dimension of scenarios and risk analysis. Surprisingly, there is certainly no direct link between increased scientific understanding and a public position for or against different strategies of nuclear waste disposal. This is not due to the public being poorly informed, but rather due to cultural cognition of expertise and historical and cultural perception of hazards to regions selected to host a geologic repository. The societal and cultural dimension does not diminish the role of science, as scientific results become even more important in distinguishing

  9. Geology of the Vaalputs radioactive waste disposal site in the Republic of South Africa

    International Nuclear Information System (INIS)

    Andreoli, M.A.G.; Andersen, N.J.B.; Levin, M.; Niemand, N.

    1987-01-01

    The Vaalputs site is underlain by an extensive veneer of Tertiary and Quaternary deposits covering a crystalline basement of Precambrian age. The geological history of the area, from the oldest to the youngest event, may be summarized as follows: 1. Polyphasic ductile/ductile-brittle deformation and 1 100 Ma old granulite facies metamorphism of a (volcano) sedimentary sequence, and of associated syntectonic to late-tectonic granitic and basic intrusions. 2. Deposition of glacial tillite after a long erosional hiatus in Karoo (Permian) times. The preservation of these rocks is limited to down-faulted structural blocks within the area investigated. 3. Lower Tertiary rejuvenation of older faults and shear zones, accompanied by kimberlitic volcanism, resulted in the uplift of the Kamiesberge mountain range west of the site. Intense erosion of these mountains shed abundant detritus, which accumulated in tectonically controlled troughs and fans. 4. From ca. 25 Ma ago to the Present, tectonic stability and (semi)arid conditions have generally prevailed, leading to an extensive thin cover of calcrete and wind-blown Kalahari sands. The unfaulted, highly impermeable nature of the Vaalputs formation renders it very suitable for the safe disposal of low- to medium-level radioactive waste in the area selected. However, the numerous faults and shear zones in the granitic and gneissic basement will need in-depth investigations should a high-level radwaste repository be required

  10. Thermal impact of waste emplacement and surface cooling associated with geologic disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Wang, J.S.Y.; Mangold, D.C.; Spencer, R.K.; Tsang, C.F.

    1982-08-01

    The thermal effects associated with the emplacement of aged radioactive wastes in a geologic repository were studied, with emphasis on the following subjects: the waste characteristics, repository structure, and rock properties controlling the thermally induced effects; the current knowledge of the thermal, thermomechanical, and thermohydrologic impacts, determined mainly on the basis of previous studies that assume 10-year-old wastes; the thermal criteria used to determine the repository waste loading densities; and the technical advantages and disadvantages of surface cooling of the wastes prior to disposal as a means of mitigating the thermal impacts. The waste loading densities determined by repository designs for 10-year-old wastes are extended to older wastes using the near-field thermomechanical criteria based on room stability considerations. Also discussed are the effects of long surface cooling periods determined on the basis of far-field thermomechanical and thermohydrologic considerations. The extension of the surface cooling period from 10 years to longer periods can lower the near-field thermal impact but have only modest long-term effects for spent fuel. More significant long-term effects can be achieved by surface cooling of reprocessed high-level waste.

  11. Fast neutron incineration as an alternative to geologic disposal: the Rubbia proposal

    International Nuclear Information System (INIS)

    Varley, James.

    1997-01-01

    The Energy Amplifier is a ''fast neutron non-critical device'' conceived by Professor Carlo Rubbia and is described as the outcome of a mature cross-fertilisation between modern accelerators and nuclear power. In its currently proposed manifestation it uses thorium and actinite waste as fuel and molten lead for cooling. The lead also acts as a built-in spallation neutron source in the reactor core. Protons from the accelerator are beamed into the spallation region of the core where they produce large numbers of neutrons. These generate heat by nuclear cascades rather than by the self-sustaining chain reaction of a conventional nuclear reactor and the amount of power produced is controlled by the beam current. The basic principle was demonstrated in an experiment at CERN in 1994. The Energy Amplifier has passive safety features, relying only on natural convection for the lead coolant and with cut-off of the proton beam by overflowing lead should the system overheat. A recent discovery has shown that in addition to incinerating transuranic elements and generating a large amount of energy, the system has the potential to transmute long-lived radioactive products from LWRs. This could virtually eliminate the need for geological disposal repositories. The Energy Amplifier would draw on a number of research strands and technologies from around the world. Funding is now being sought to build a 100 MWt prototype. (UK)

  12. Thermal impact of waste emplacement and surface cooling associated with geologic disposal of nuclear waste

    International Nuclear Information System (INIS)

    Wang, J.S.Y.; Mangold, D.C.; Spencer, R.K.; Tsang, C.F.

    1982-08-01

    The thermal effects associated with the emplacement of aged radioactive wastes in a geologic repository were studied, with emphasis on the following subjects: the waste characteristics, repository structure, and rock properties controlling the thermally induced effects; the current knowledge of the thermal, thermomechanical, and thermohydrologic impacts, determined mainly on the basis of previous studies that assume 10-year-old wastes; the thermal criteria used to determine the repository waste loading densities; and the technical advantages and disadvantages of surface cooling of the wastes prior to disposal as a means of mitigating the thermal impacts. The waste loading densities determined by repository designs for 10-year-old wastes are extended to older wastes using the near-field thermomechanical criteria based on room stability considerations. Also discussed are the effects of long surface cooling periods determined on the basis of far-field thermomechanical and thermohydrologic considerations. The extension of the surface cooling period from 10 years to longer periods can lower the near-field thermal impact but have only modest long-term effects for spent fuel. More significant long-term effects can be achieved by surface cooling of reprocessed high-level waste

  13. Preliminary conceptual designs for advanced packages for the geologic disposal of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Westerman, R.E.

    1979-04-01

    The present study assumes that the spent fuel will be disposed of in mined repositories in continental geologic formations, and that the post-emplacement control of the radioactive species will be accomplished independently by both the natural barrier, i.e., the geosphere, and the engineered barrier system, i.e., the package components consisting of the stabilizer, the canister, and the overpack; and the barrier components external to the package consisting of the hole sleeve and the backfill medium. The present document provides an overview of the nature of the spent fuel waste; the general approach to waste containment, using the defense-in-depth philosophy; material options, both metallic and nonmetallic, for the components of the engineered barrier system; a set of strawman criteria to guide the development of package/engineered barrier systems; and four preliminary concepts representing differing approaches to the solution of the containment problem. These concepts use: a corrosion-resistant meta canister in a special backfill (2 barriers); a mild steel canister in a corrosion-resistant metallic or nonmetallic hole sleeve, surrounded by a special backfill (2 barriers); a corrosion-resistant canister and a corrosion-resistant overpack (or hole sleeve) in a special backfill (3 barriers); and a mild steel canister in a massive corrosion-resistant bore sleeve surrounded by a polymer layer and a special backfill (3 barriers). The lack of definitive performance requirements makes it impossible to evaluate these concepts on a functional basis at the present time.

  14. A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 2

    International Nuclear Information System (INIS)

    Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

    1993-01-01

    This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified, of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the second

  15. Bentonite analogue research related to geological disposal of radioactive waste: current status and future outlook

    Energy Technology Data Exchange (ETDEWEB)

    Reijonen, H.M. [Saanio and Rickkola Oy, Helsinki (Finland); Russel, A.W. [Bedrock Geosciences, Auenstein (Switzerland)

    2015-06-15

    The practice of utilising natural analogues in assessing the long-term behaviour of various components of geological repositories for radioactive waste is already well established in most disposal programmes. Numerous studies on bentonites, focussing on bentonite interaction with other components of the engineered barrier system and a range of host rock environments, are present in the literature. In this article, recent bentonite natural analogue studies are briefly reviewed, and gaps in the current literature identified, with the aim of (1) suggesting where relevant new information could be obtained by data mining published bentonite natural analogue studies with a new focus on current safety case requirements, (2) collecting relevant information by revisiting known bentonite analogue sites and conducting investigations with more appropriate analytical techniques, and (3) identifying novel study sites where, for example, bentonite longevity in very dilute to highly saline groundwater conditions can be studied. It must be noted that the use of natural analogues in safety case development is likely to be site and repository design-specific in nature and thus emphasis is placed on the appropriate use of relevant natural analogue data on bentonite longevity. (authors)

  16. A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 1

    International Nuclear Information System (INIS)

    Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

    1993-01-01

    This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the first

  17. Risk methodology for geologic disposal of radioactive waste: asymptotic properties of the environmental transport model

    International Nuclear Information System (INIS)

    Helton, J.C.; Brown, J.B.; Iman, R.L.

    1981-02-01

    The Environmental Transport Model is a compartmental model developed to represent the surface movement of radionuclides. The purpose of the present study is to investigate the asymptotic behavior of the model and to acquire insight with respect to such behavior and the variables which influence it. For four variations of a hypothetical river receiving a radionuclide discharge, the following properties are considered: predicted asymptotic values for environmental radionuclide concentrations and time required for environmental radionuclide concentrations to reach 90% of their predicted asymptotic values. Independent variables of two types are used to define each variation of the river: variables which define physical properties of the river system (e.g., soil depth, river discharge and sediment resuspension) and variables which summarize radionuclide properties (i.e., distribution coefficients). Sensitivity analysis techniques based on stepwise regression are used to determine the dominant variables influencing the behavior of the model. This work constitutes part of a project at Sandia National Laboratories funded by the Nuclear Regulatory Commission to develop a methodology to assess the risk associated with geologic disposal of radioactive waste

  18. Evaluation of uncertainty associated with parameters for long-term safety assessments of geological disposal

    International Nuclear Information System (INIS)

    Yamaguchi, Tetsuji; Minase, Naofumi; Iida, Yoshihisa; Tanaka, Tadao; Nakayama, Shinichi

    2005-01-01

    This paper describes the current status of our data acquisition on quantifying uncertainties associated with parameters for safety assessment on groundwater scenarios for geological disposal of radioactive wastes. First, sources of uncertainties and the resulting priority in data acquisition were briefed. Then, the current status of data acquisition for quantifying the uncertainties in assessing solubility, diffusivity in bentonite buffer and distribution coefficient on rocks is introduced. The uncertainty with the solubility estimation is quantified from that associated with thermodynamic data and that in estimating groundwater chemistry. The uncertainty associated with the diffusivity in bentonite buffer is composed of variations of relevant factors such as porosity of the bentonite buffer, montmorillonite content, chemical composition of pore water and temperature. The uncertainty of factors such as the specific surface area of the rock, pH, ionic strength, carbonate concentration in groundwater compose uncertainty of the distribution coefficient of radionuclides on rocks. Based on these investigations, problems to be solved in future studies are summarized. (author)

  19. Overview of the site selection, geological and engineering problems facing radioactive waste disposal at Sellafield, UK

    International Nuclear Information System (INIS)

    Haszeldine, R.S.; Smythe, D.K.

    1996-01-01

    UK Nirex Ltd is the company charged with finding a suitable site for the disposal of radioactive waste in the United Kingdom. Since 1991, Nirex has concentrated its site investigation work at Longlands Farm which is owned by British Nuclear Fuels Ltd and is near their Sellafield site. Planning permission was sought for the development of an underground Rock Characterisation Facility (RCF) at the site in 1994. A public Planning Inquiry began in September 1995. A wide range of scientific and technical objections were put by expert witnesses against the Nirex Proposal. These witnesses were co-ordinated by three Objecting Organisations - Cumbria County Council, Friends of the Earth and Greenpeace. Their written evidence is presented in this book. The grounds of the objections include: the inadequacy of the methodology adopted by Nirex for site selection and investigation; The unsuitability of the site geology, hydrology and geochemistry; that construction of the RCF would destroy the data essential to deciding site suitability; that the RCF would provide a conduit for the release of radioactivity; a number of features in the Nirex risk assessment that would lead to an underestimation of the potential risks of a repository at this site. (UK)

  20. Bentonite analogue research related to geological disposal of radioactive waste: current status and future outlook

    International Nuclear Information System (INIS)

    Reijonen, H.M.; Russel, A.W.

    2015-01-01

    The practice of utilising natural analogues in assessing the long-term behaviour of various components of geological repositories for radioactive waste is already well established in most disposal programmes. Numerous studies on bentonites, focussing on bentonite interaction with other components of the engineered barrier system and a range of host rock environments, are present in the literature. In this article, recent bentonite natural analogue studies are briefly reviewed, and gaps in the current literature identified, with the aim of (1) suggesting where relevant new information could be obtained by data mining published bentonite natural analogue studies with a new focus on current safety case requirements, (2) collecting relevant information by revisiting known bentonite analogue sites and conducting investigations with more appropriate analytical techniques, and (3) identifying novel study sites where, for example, bentonite longevity in very dilute to highly saline groundwater conditions can be studied. It must be noted that the use of natural analogues in safety case development is likely to be site and repository design-specific in nature and thus emphasis is placed on the appropriate use of relevant natural analogue data on bentonite longevity. (authors)

  1. A directory of computer programs for assessment of radioactive waste disposal in geological formations

    International Nuclear Information System (INIS)

    Broyd, T.W.; Dean, R.B.; Hobbs, G.D.; Knowles, N.C.; Putney, J.M.; Wrigley, J.

    1984-01-01

    This Directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, stress analysis, heat transfer, groundwater flow and radionuclide transport. Biosphere modelling, surface water flow and risk analysis are not covered. A total of 248 programs are identified, of which 50 are reviewed in detail, 134 in summary and 64 in tabular fashion. The directory has been compiled using a combination of literature searches, telephone and postal correspondence and meetings with recognised experts in the respective areas of work covered. It differs from previous reviews of computer programs for similar topics areas in two main respects. Firstly, the method of obtaining information has resulted in program descriptions of considerable breadth and detail. Secondly, the Directory has concentrated wherever possible on European codes, whereas most previous work of this nature has looked solely at programs developed in North America. The reviews are presented in good faith, but it has not been possible to run any of the programs on a computer, and so truly objective comparisons may not be made. Finally, although the Directory is specific to the post-closure assessment of a repository site, some of the programs described could also be used in other areas of repository analysis (eg repository design)

  2. US Geological Survey research in radioactive waste disposal: Fiscal Years, 1983, 1984, and 1985

    International Nuclear Information System (INIS)

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

    1986-01-01

    The USGS has been assisting the DOE in evaluating the suitability of the Yucca Mountain area, located on and adjacent to the Nevada Test Site (NTS) and about 160 km northwest of Las Vegas, as a possible repository site for the disposal of commercially generated high-level radioactive wastes and wastes from DOE facilities. An essential part of this work is defining the geology and hydrology of the area in order to assess the potential for the transport of radionuclides from a repository to the human environment. In addition, the potential for disruption of a repository as a result of volcanic or tectonic activity or accelerated erosion is being evaluated. As part of the Nevada Nuclear Waste Storage Investigations (NNWSI) project, the USGS is performing multi-disciplinary studies involving detailed surface mapping, surface geophysics, exploratory drilling, borehole geophysics, and topical studies of hydrology, climate, and tectonics. Studies are being performed to assess the potential for faulting, damaging earthquakes, recurrence of volcanism, and local acceleration of erosion in parts of the southern Great Basin. Hydrologic investigations are directed to determination of present and past hydrologic regimes of the NTS and vicinity in order to predict the potential for ground-water transport of radioactive waste from a repository in Yucca Mountain to the accessible environment. Paleoclimatic studies are also being performed to aid in predicting future climate in the NTS vicinity

  3. Application of lifecycle management to design of the UK geological disposal facility

    International Nuclear Information System (INIS)

    Rendell, Philip G.P.; O'Grady, Henry J.P.; Currie, Malcolm F.

    2011-01-01

    The Radioactive Waste Management Directorate (RWMD) of the United Kingdom's (UK) Nuclear Decommissioning Authority (NDA) has been given the responsibility for delivery of a Geological Disposal Facility (GDF) for the UK's higher activity wastes in accordance with government policy. As part of this process, the RWMD has developed a project lifecycle, which addresses the overall lifecycle of the GDF in terms of five phases, from Preparatory Studies through to Operation and finally Closure, and is developing a staged approach to engineering design. The Engineering Design Process is broken down into seven stages, encompassing option development, requirements definition and preliminary and detailed design through to 'design development during closure'. Each stage finishes with a formally defined milestone (a 'gate') comprising a technical review and a specific set of engineering deliverables. This paper describes the background to the UK GDF development programme, the organisational issues associated with the RWMD's evolving role, the relationship between the top-level UK Government's Managing Radioactive Waste Safely programme and the RWMD engineering lifecycle, the formal reviews, the milestones and the overall contribution this makes to RWMD organisational development and UK regulatory approval. It also describes some of the lessons learnt. (author)

  4. Evaluation of performance of barrier materials in geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Sasakura, Takeshi; Kobayashi, Ichizo

    2004-01-01

    It is important to evaluate the hydraulic and mechanical performance of barrier materials for geological disposal of radioactive waste. Many experiments on the hydraulic and mechanical performance of barrier materials have been implemented. However, both the ordinary water head-controlled permeability test for evaluating hydraulic performance and the oedometer test for obtaining the mechanical properties are usually needed. In this study, the flow pump permeability test was applied to various barrier materials with the purpose of quickly evaluating their hydraulic performance. The flow pump permeability test was shown to be applicable to every barrier material employed in this study, of which the coefficient of permeability ranged from 10-7 to 10-14 m/sec. The time needed to obtain the coefficient of permeability was about 1/8 that of ordinary head-controlled permeability tests. The resulting coefficient of permeability was more accurate than that from the standard water head-controlled permeability test. Moreover, the bentonite-engineered barrier materials were subjected to a constant strain rate consolidation test, which is a method to quickly evaluate the mechanical performance. The results of the consolidation tests were consistent with the results of the oedometer tests and the necessary time for the test was reduced to only four days even in case of Na-ben-tonite, for which a couple of months was necessary with the standard oedometer test. (author)

  5. 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)

  6. Scenarios used for the evaluations of the safety of a site for adioactive waste disposal in deep geologic formations

    International Nuclear Information System (INIS)

    Escalier des Orres, P.; Devillers, C.; Cernes, A.

    1989-11-01

    The selection and qualification procedure of a site for radioactive wastes disposal in a deep geologic formation, has begun in France in the early eighties. The public authorities, on ANDRA's proposal, has preselected in 1987 four sites, each of them coppresponding to a type, of geologic formations (granite, clay, salt and shale). Within two years, one of these sites will be chosen for the location of an undergound laboratory. The safety analysis for the site's qualification uses evolution scenarios of the repository and its environment, chosen according to a deterministic method. With an appropriate detail level, are defined a reference scenario and scenario with random events [fr

  7. Possible effects of UO2 oxidation on light water reactor spent fuel performance in long-term geologic disposal

    International Nuclear Information System (INIS)

    Almassy, M.Y.; Woodley, R.E.

    1982-08-01

    Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO 2 ) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO 2 oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented

  8. 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

  9. North Carolina Geological Survey's role in siting a low-level radioactive (LLRW) waste disposal facility in North Carolina

    International Nuclear Information System (INIS)

    Reid, J.C.; Wooten, R.M.; Farrell, K.M.

    1993-01-01

    The Southeast Compact Commission in 1986 selected North Carolina to host the Southeast's LLRW disposal facility for the next twenty years. The North Carolina Geological Survey (NCGS) for six years has played a major role in the State's efforts by contributing to legislation and administrative code, policy, technical oversight and surveillance and regulation as a member of the State's regulatory team. Future activities include recommendation of the adequacy of characterization and site performance pursuant to federal code, state general statutes and administrative code, and review of a license application. Staff must be prepared to present testimony and professional conclusions in court. The NCGS provides technical advice to the Division of Radiation Protection (DRP), the regulatory agency which will grant or deny a LLRW license. The NCGS has not participated in screening the state for potential sites to minimize bias. The LLRW Management Authority, a separate state agency siting the LLRW facility, hired a contractor to characterize potential sites and to write a license application. Organizational relationships enable the NCGS to assist the DRP in its regulatory role without conflict of interest. Disposal facilities must be sited to ensure safe disposal of LLRW. By law, the siting of a LLRW disposal facility is primarily a geological, rather than an engineering, effort. Federal and State statutes indicate a site must be licensable on its own merits. Engineered barriers cannot make a site licensable. The project is 3 years behind schedule and millions of dollars over budget. This indicates the uncertainty and complexity inherent in siting such as facility, the outcome of which cannot be predicted until site characterization is complete, the license application reviewed and the performance assessment evaluated. State geological surveys are uniquely qualified to overview siting of LLRW facilities because of technical expertise and experience in the state's geology

  10. International Socio-Technical Challenges for Geological Disposal (InSOTEC): Project Aims and Preliminary Results - 12236

    Energy Technology Data Exchange (ETDEWEB)

    Bergmans, Anne; Schroeder, Jantine [University of Antwerp, Faculty of Political and Social Sciences, 2000 Antwerp (Belgium); Simmons, Peter [University of East Anglia, School of Environmental Sciences, NR4 7TJ Norwich (United Kingdom); Barthe, Yannick; Meyer, Morgan [CNRS, Ecole des Mines, 75272 Paris (France); Sundqvist, Goeran [Universitetet i Oslo, Centre for Studies of Technology, Innovation and Culture, 0851 Oslo (Norway); Martell, Merixell [MERIENCE Strategic Thinking, 08734 Olerdola (Spain); Kallenbach-Herbert, Beate [Oeko Institut, 64295 Darmstadt (Germany)

    2012-07-01

    InSOTEC is a social sciences research project which aims to generate a better understanding of the complex interplay between the technical and the social in radioactive waste management and, in particular, in the design and implementation of geological disposal. It currently investigates and analyses the most striking socio-technical challenges to implementing geological disposal of radioactive waste in 14 national programs. A focus is put on situations and issues where the relationship between the technical and social components is still unstable, ambiguous and controversial, and where negotiations are taking place in terms of problem definitions and preferred solutions. Such negotiations can vary from relatively minor contestation, over mild commotion, to strong and open conflicts. Concrete examples of socio-technical challenges are: the question of siting, introducing the notion of reversibility / retrievability into the concept of geological disposal, or monitoring for confidence building. In a second stage the InSOTEC partners aim to develop a fine-grained understanding of how the technical and the social influence, shape, build upon each other in the case of radioactive waste management and the design and implementation of geological disposal. How are socio-technical combinations in this field translated and materialized into the solutions finally adopted? With what kinds of tools and instruments are they being integrated? Complementary to providing better theoretical insight into these socio-technical challenges/combinations, InSOTEC aims to provide concrete suggestions on how to address these within national and international contexts. To this end, InSOTEC will deliver insights into how mechanisms for interaction between the technical community and a broad range of socio-political actors could be developed. (authors)

  11. Factors affecting public and political acceptance for the implementation of geological disposal

    International Nuclear Information System (INIS)

    Neerdael, Bernard

    2007-01-01

    The main objective of this paper is to identify conditions which affect public concern (either increase or decrease) and political acceptance for developing and implementing programmes for geologic disposal of long-lived radioactive waste. It also looks how citizens and relevant actors can be associated in the decision making process in such a way that their input is enriching the outcome towards a more socially robust and sustainable solution. Finally, it aims at learning from the interaction how to optimise risk management addressing needs and expectations of the public and of other relevant stakeholders. In order to meet these objectives, factors of relevance for societal acceptance conditions are identified, described and analysed. Subsequently these factors are looked for in the real world of nuclear waste management through cases in several countries. The analysis is conducted for six stages of a repository programme and implementation process, from policy development to the realisation of the repository itself. The diversity of characteristics of such contexts increases insight in the way society and values of reference are influencing technological decision making. These interrelated factors need to be integrated in step by step decision making processes as emerging the last years in HLW disposal management. In the conclusions, the effect of each factor on acceptance is derived from the empirical record. In the course of carrying out this analysis, it became clear that acceptance had a different meaning in the first three stages of the process, more generic and therefore mainly discussed at policy level and the other stages, by nature more site-specific, and therefore requesting both public and political acceptance. Experience as clearly addressed in this report has shown that a feasible solution has its technical dimension but that 'an acceptable solution' always will have a combined technical and social dimension. If the paper provides tentative answers

  12. Red-impact project: First results of the evaluations of the impact of P and T on geological disposal

    International Nuclear Information System (INIS)

    Marivoet, Jan; Vokal, Antonin; Gudowski, Waclaw

    2006-01-01

    The Red-Impact project (Impact of partitioning, transmutation and waste reduction technologies on the final nuclear waste disposal) is a research project in the 6. Framework Programme of the European Commission. The main objective of the project is to assess the impact of partitioning and transmutation (P and T) on geological disposal and waste management. The project started with the identification of a number of representative fuel cycle scenarios. Five basis scenarios are considered for the evaluations: 2 industrial scenarios and 3 innovative scenarios. Mass flow schemes have been prepared for each basis fuel cycle scenario and the corresponding neutronic calculations have been made. A first list of performance indicators that will be calculated or estimated in the project has been prepared. As a first step the impact of 2 fuel cycle scenarios, the reference 'open cycle' scenario and of the innovative 'fast neutron Gen IV' scenario, on geological repositories in granite and clay formations have been evaluated. The results obtained show that the introduction of innovative fuel cycle scenarios can result in a considerable reduction of the needed size of the geological repository. However, the impact on the radiological consequences is rather limited. Indeed, the maximum dose, which is expected to occur a few tens of thousands year after the disposal of the waste, is essentially due to fission products and their amount is about proportional to the heat generated by nuclear fissions. (authors)

  13. 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)

  14. Study on improvement in reliability of inventory assessment in vitrified waste for long-term safety of geological disposal

    International Nuclear Information System (INIS)

    Ishikawa, Masumi; Kaneko, Satoru; Kitayama, Kazumi; Ishiguro, Katsuhiko; Ueda, Hiroyoshi; Wakasugi, Keiichiro; Shinohara, Nobuo; Okumura, Keisuke; Chino, Masamichi; Moriya, Noriyasu

    2009-01-01

    Since quality control issues for vitrified waste are defined mainly with the focus on the transport and interim storage of the waste rather than the long-term safety of geological disposal, they do not cover inventories of long-lived nuclides that are of most interest in the safety assessment of geological disposal. Therefore, we suggest a flow chart for the assessment of inventories of long-lived nuclides in the vitrified waste focusing on the measured values. This includes an indirect assessment with indicative nuclides that have been already measured in the returned vitrified wastes from abroad. In order to apply this flow chart for commercial operation, its applicability should be examined for cases with a variation in burn-up history and with an uncertainty associated with carry-over fraction at reprocessing. We started an R and D program to examine the applicability as well as to improve the reliability of the nuclide generation/decay code and the nuclear data library using liquid waste from spent fuel with a clear irradiation history. To solve the issue of quality control for vitrified waste, a comprehensive study is needed in aspects not only of geological disposal field but also of operation of a nuclear power plant, reprocessing of spent fuel and vitrification of liquid waste. This study is a pioneering study conducted to integrate them. (author)

  15. Treatment and final disposal of nuclear waste. Programme for encapsulation, deep geological disposal, and research, development and demonstration

    International Nuclear Information System (INIS)

    1995-09-01

    Programs for RD and D concerning disposal of radioactive waste are presented. Main topics include: Design, testing and manufacture of canisters for the spent fuels; Design of equipment for deposition of waste canisters; Material and process for backfilling rock caverns; Evaluation of accuracy and validation of methods for safety analyses; Development of methods for defining scenarios for the safety analyses. 471 refs, 67 figs, 21 tabs

  16. Treatment and final disposal of nuclear waste. Programme for encapsulation, deep geological disposal, and research, development and demonstration

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    Programs for RD and D concerning disposal of radioactive waste are presented. Main topics include: Design, testing and manufacture of canisters for the spent fuels; Design of equipment for deposition of waste canisters; Material and process for backfilling rock caverns; Evaluation of accuracy and validation of methods for safety analyses; Development of methods for defining scenarios for the safety analyses. 471 refs, 67 figs, 21 tabs.

  17. An integrated approach to geological disposal of UK wastes containing carbon-14

    International Nuclear Information System (INIS)

    Vines, Sarah; Lever, David

    2013-01-01

    Carbon-14 is a key radionuclide in the assessment of the safety of a geological disposal facility for radioactive waste because of the calculated assessment of the radiological consequences of gaseous carbon-14 bearing species [i]. It may be that such calculations are based on overly conservative assumptions and that better understanding could lead to considerably reduced assessment of the radiological consequences from these wastes. Alternatively, it may be possible to mitigate the impact of these wastes through alternative treatment, packaging or design options. The Radioactive Waste Management Directorate of the UK's Nuclear Decommissioning Authority (NDA RWMD) has established an integrated project team in which the partners are working together to develop a holistic approach to carbon-14 management in the disposal system [ii]. For a waste stream containing carbon-14 to be an issue: There must be a significant inventory of carbon-14 in the waste stream; and That waste stream has to generate carbon-14 bearing gas; and a bulk gas phase has to entrain the carbon-14 bearing gas: and these gases must migrate through the engineered barriers in significant quantities; and these gases must migrate through the overlying geological environment (either as a distinct gas phase or as dissolved gas); and these gases must interact with materials in the biosphere (i.e. plants) in a manner that leads to significant doses and risks to exposed groups or potentially exposed groups. The project team has developed and used this 'and' approach to structure and prioritise the technical work and break the problem down in a manageable way. We have also used it to develop our approach to considering alternative treatment, packaging and design options. For example, it may be possible to pre-treat some wastes to remove some of the inventory or to segregate other wastes so that they are removed from any bulk gas phase which might facilitate migration through the geosphere

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

    International Nuclear Information System (INIS)

    2006-11-01

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

  19. An integrated approach to geological disposal of UK wastes containing carbon-14

    Energy Technology Data Exchange (ETDEWEB)

    Vines, Sarah [Nuclear Decommissioning Authority, Harwell, Oxfordshire (United Kingdom); Lever, David [AMEC, Harwell, Oxfordshire (United Kingdom)

    2013-07-01

    Carbon-14 is a key radionuclide in the assessment of the safety of a geological disposal facility for radioactive waste because of the calculated assessment of the radiological consequences of gaseous carbon-14 bearing species [i]. It may be that such calculations are based on overly conservative assumptions and that better understanding could lead to considerably reduced assessment of the radiological consequences from these wastes. Alternatively, it may be possible to mitigate the impact of these wastes through alternative treatment, packaging or design options. The Radioactive Waste Management Directorate of the UK's Nuclear Decommissioning Authority (NDA RWMD) has established an integrated project team in which the partners are working together to develop a holistic approach to carbon-14 management in the disposal system [ii]. For a waste stream containing carbon-14 to be an issue: There must be a significant inventory of carbon-14 in the waste stream; and That waste stream has to generate carbon-14 bearing gas; and a bulk gas phase has to entrain the carbon-14 bearing gas: and these gases must migrate through the engineered barriers in significant quantities; and these gases must migrate through the overlying geological environment (either as a distinct gas phase or as dissolved gas); and these gases must interact with materials in the biosphere (i.e. plants) in a manner that leads to significant doses and risks to exposed groups or potentially exposed groups. The project team has developed and used this 'and' approach to structure and prioritise the technical work and break the problem down in a manageable way. We have also used it to develop our approach to considering alternative treatment, packaging and design options. For example, it may be possible to pre-treat some wastes to remove some of the inventory or to segregate other wastes so that they are removed from any bulk gas phase which might facilitate migration through the geosphere

  20. Production, consumption and transport of gases in deep geological repositories according to the Swiss disposal concept

    International Nuclear Information System (INIS)

    Diomidis, N; Cloet, V.; Leupin, O.X.; Marschall, P.; Poller, A.; Stein, M.

    2016-12-01

    In a deep geological repository for radioactive waste, in absence of oxygen and in presence of water, corrosion of various metals and alloys will lead to the formation of hydrogen. If present, organic materials may slowly degrade and generate carbon dioxide, methane and other gaseous species. Depending on local conditions, gaseous species can be consumed by chemical reactions and by microbial activity. If the resulting rate of gas generation exceeds the rate of migration of dissolved gas molecules in the pores of the engineered barriers or the host rock, the solubility limit of the gas will eventually be exceeded and the formation of a discrete gas phase will occur. Gases could continue to accumulate until the pressure becomes sufficient to be released in gaseous form. This report deals with the evolution of gas-related processes that can influence the long-term behaviour and safety of low- and intermediate-level waste (L/ILW) and high-level waste (HLW) repositories in Opalinus Clay. The main aim is to present a synthesis of processes and phenomena related to repository-produced gases and to assess their influence on repository performance. A current overview of gas sources, reactions and interactions, generation, consumption, and transport is provided. Furthermore, current scientific understanding is used to define safety function indicators and criteria, which are employed to evaluate the potential influence of repository-generated gas on safety-relevant properties of engineered and natural barriers. The assessment of gas generation, consumption and transport is addressed separately for the HLW and the L/ILW deep geological repositories. The employed methodology, which is common for both repository types, consists of the description and quantification of the potential gas sources, which include the waste, barrier components such as disposal canisters and other gas-generating repository components, and of the processes and reactions leading to the generation or

  1. Production, consumption and transport of gases in deep geological repositories according to the Swiss disposal concept

    Energy Technology Data Exchange (ETDEWEB)

    Diomidis, N; Cloet, V.; Leupin, O.X.; Marschall, P.; Poller, A.; Stein, M.

    2016-12-15

    In a deep geological repository for radioactive waste, in absence of oxygen and in presence of water, corrosion of various metals and alloys will lead to the formation of hydrogen. If present, organic materials may slowly degrade and generate carbon dioxide, methane and other gaseous species. Depending on local conditions, gaseous species can be consumed by chemical reactions and by microbial activity. If the resulting rate of gas generation exceeds the rate of migration of dissolved gas molecules in the pores of the engineered barriers or the host rock, the solubility limit of the gas will eventually be exceeded and the formation of a discrete gas phase will occur. Gases could continue to accumulate until the pressure becomes sufficient to be released in gaseous form. This report deals with the evolution of gas-related processes that can influence the long-term behaviour and safety of low- and intermediate-level waste (L/ILW) and high-level waste (HLW) repositories in Opalinus Clay. The main aim is to present a synthesis of processes and phenomena related to repository-produced gases and to assess their influence on repository performance. A current overview of gas sources, reactions and interactions, generation, consumption, and transport is provided. Furthermore, current scientific understanding is used to define safety function indicators and criteria, which are employed to evaluate the potential influence of repository-generated gas on safety-relevant properties of engineered and natural barriers. The assessment of gas generation, consumption and transport is addressed separately for the HLW and the L/ILW deep geological repositories. The employed methodology, which is common for both repository types, consists of the description and quantification of the potential gas sources, which include the waste, barrier components such as disposal canisters and other gas-generating repository components, and of the processes and reactions leading to the generation or

  2. A review of near-field mass transfer in geologic disposal systems

    International Nuclear Information System (INIS)

    Pigford, T.H.; Chambre, P.L.; Lee, W.W.L.

    1990-02-01

    In this report we summarize the analyses of the time-dependent mass transfer of radionuclides from a waste solid into surrounding porous or fractured media that have been developed at the University of California, Berkeley. For each analysis we describe the conceptual model, we present the governing equations and the resulting analytic solutions, and we illustrate the results. Designers of geologic disposal systems for solid waste must predict the long-term time-dependent rate of dissolution of toxic contaminants in ground water, to provide the source term for predicting the later transport of these contaminants to the environment. Mass-transfer analysis is being used to predict rates of dissolution and release of radioactive constituents in future repositories for high-level radioactive waste, and it has been applied to predict the life of a copper container for high-level radioactive waste. Mechanistic analysis of mass-transfer is based on well-established theory of diffusive-convective transport. Its application requires experimental measurement of well-defined parameters such as porosity, solubility, diffusion coefficient, and pore velocity. Our first analysis assumed a waste solid in direct contact with porous rock. Subsequently we analyzed the more realistic situations of backfill between the waste and rock, rock with discrete fractures as well as pores, and the effects of waste constituents of high solubility. Those dealing with specifically with mass transfer in the near field are presented here. In order to have a consistent set of notation within this review, some of the notation here is different than in the reports cited. 71 refs., 47 figs., 7 tabs

  3. Numerical investigation of high level nuclear waste disposal in deep anisotropic geologic repositories

    KAUST Repository

    Salama, Amgad

    2015-11-01

    One of the techniques that have been proposed to dispose high level nuclear waste (HLW) has been to bury them in deep geologic formations, which offer relatively enough space to accommodate the large volume of HLW accumulated over the years since the dawn of nuclear era. Albeit the relatively large number of research works that have been conducted to investigate temperature distribution surrounding waste canisters, they all abide to consider the host formations as homogeneous and isotropic. While this could be the case in some subsurface settings, in most cases, this is not true. In other words, subsurface formations are, in most cases, inherently anisotropic and heterogeneous. In this research, we show that even a slight difference in anisotropy of thermal conductivity of host rock with direction could have interesting effects on temperature fields. We investigate the effect of anisotropy angle (the angle the principal direction of anisotropy is making with the coordinate system) on the temperature field as well as on the maximum temperature attained in different barrier systems. This includes 0°, 30°, 45°, 60°, and 90°in addition to the isotropic case as a reference. We also consider the effect of anisotropy ratio (the ratio between the principal direction anisotropies) on the temperature fields and maximum temperature history. This includes ratios ranging between 1.5 and 4. Interesting patterns of temperature fields and profiles are obtained. It is found that the temperature contours are aligned more towards the principal direction of anisotropy. Furthermore the peak temperature in the buffer zone is found to be larger the smaller the anisotropy angle and vice versa. © 2015 Elsevier Ltd. All rights reserved.

  4. Preservation of Records, Knowledge and Memory across Generations (RK and M). Monitoring of Geological Disposal Facilities - Technical and Societal Aspects

    International Nuclear Information System (INIS)

    2014-01-01

    The OECD Nuclear Energy Agency (NEA) Radioactive Waste Management Committee (RWMC) Project on 'Preservation of Records, Knowledge and Memory across generations (RK and M)' (2011-2014) explores and aims to develop guidance on regulatory, policy, managerial, and technical aspects of long-term preservation of records, knowledge and memory of deep geological disposal facilities. While official responsibility for the preservation of records, knowledge and memory must remain with institutions, it is likely that local communities do or will have an important pragmatic role in maintaining the memory of a repository, e.g., by engaging at some level in its continued oversight. Monitoring - by collecting, interpreting and keeping data on a continuous basis - would serve the purpose of preserving records, knowledge and memory and continuous oversight. In order to tackle the subject it is important, on the one hand, to describe the role of monitoring in a technical perspective and, on the other, to understand the expectations of local stakeholders regarding monitoring. The present study report should therefore meet three objectives: - To present in a comprehensive way the general monitoring information, practices and approaches used in the various national geological disposal programmes and elaborated in a number of international projects; - To explore the role, needs and expectations of local communities regarding monitoring and RK and M preservation of deep geological repositories; - Based on the above review, to identify lessons learned and the rationale for monitoring geological disposal projects throughout their life-cycle stages. This report is based on two studies: an NEA internal report entitled 'Monitoring of Geological Disposal Facilities (August 2013)' which provides an overview on technical aspects of monitoring and an NEA public report entitled 'Local Communities' Expectations and Demands on Monitoring and the Preservation of Records, Knowledge and Memory of a Deep

  5. Appraisal of the physical and dynamic state of the Mayak operations geological environment with a view to underground radwaste disposal

    International Nuclear Information System (INIS)

    Velichkin, V.I.; Petrov, V.A.; Tarasov, N.N.; Poluektov, V.V.; Kochkin, B.T.; Asadulin, A.A.; Volkov, A.B.

    1995-01-01

    The results of the research into geological structure, geomorphology, paleotectonics, mineralogy and petrography, petrophysics and petrochemistry of the site occupied by the Mayak radiochemical operations are presented. The research was aimed at the identification of the site for underground disposal of solidified high-level radioactive wastes (HLW). Geotectonic position of the district in the regional structures is shown, and paragenesis of fold and fault structures formed at the various stages and under various conditions of strains in the geological environment are described. The internal structure, nature and rates of the development of the processes of metamorphic and hydrothermal-metasomatic transformation of the geological environment, as well as basic petrogeochemical features of the strata were brought out. Stress-strained state of the strata at the stage of Cenozoic deformations that is retained nowadays was simulated. Basic petrophysical characteristics of adjoining strata were identified. Non-uniformity of the development of fissure-pore systems in the profile of strata of volcanic and sedimentary origin and peculiarities of deformations were revealed. The given comprehensive research was recommended for the identification of geological blocks suitable in varying degrees for the HLW disposal to the district

  6. 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)

  7. 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

  8. Assessing the effects of human action on the safety of geologic disposal: the U.S. regulatory experience

    International Nuclear Information System (INIS)

    Schultheisz, D.

    2010-01-01

    There is general agreement that geologic disposal of long-lived radioactive waste provides the greatest degree of isolation from the biosphere, and hence the greatest protection for humans, over the extended time frames during which the waste presents a hazard. Geologic disposal has an additional advantage in that it does not rely on active institutional controls to maintain and protect the facility, but is instead intended to operate passively even if all knowledge of the facility is lost. Thus, geologic disposal does not rely on the questionable assumption that governmental or other responsible institutions can be maintained in perpetuity; this, however, also raises the possibility that some future human action could be taken that disrupts the repository and compromises its ability to isolate the radioactive material. It is clear, therefore, that some evaluation of this possibility must be included in the overall safety case for the facility. The nature and extent of the analysis, as well as the relative importance it is assigned within the safety case, is less clear. The U.S. Environmental Protection Agency (EPA) has applied two very different approaches to the analysis of human intrusion scenarios at geologic disposal facilities. For the Waste Isolation Pilot Plant (WIPP) in New Mexico, which accepts transuranic radioactive waste from government defence activities, realistic drilling and mining scenarios are analyzed as part of the safety assessment addressing the natural (undisturbed) evolution of the repository. (40 CFR 194.32 and 194.33) For the proposed repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada, however, a specified stylised drilling scenario is analyzed separately from the safety assessment for the undisturbed evolution of the disposal system. (40 CFR 197.25 ) What is the basis for these different approaches? How can they both be 'right'? The answer lies in the details of the two facilities, specifically

  9. Vision and framework for technical and management support to facilitate foreign spent fuel storage and geologic disposal in Russia

    International Nuclear Information System (INIS)

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

    1999-01-01

    This 'Technical and Management Support' program would facilitate the transfer of spent fuel from commercial power plants in Taiwan to a storage and geologic repository site near Krasnoyarsk, Russia. This program resolves issues of disposition of Taiwan spent fuel (including US origin fuel) and provides revenue for Russia to develop an integrated spent fuel storage and radioactive waste management system including a geologic repository. LLNL has ongoing contracts and collaborations with all the principal parties and is uniquely positioned to facilitate the development of such a program. A three-phase approach over 20 years is proposed: namely, an initial feasibility investigation followed by an engineering development phase, and then implementation

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

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  11. 2005 dossier: granite. Tome: safety analysis of the geologic disposal; Dossier 2005: granite. Tome analyse de surete du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

  12. 2005 dossier: granite. Tome: safety analysis of the geologic disposal; Dossier 2005: granite. Tome analyse de surete du stockage geologique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

  13. On the 'Interim summary of requirements and criteria for nationwide scientific screening by the geological disposal technology working group.'

    International Nuclear Information System (INIS)

    Tochiyama, Osamu

    2016-01-01

    In order to make progress on the permanent geological disposal of high-level radioactive waste, the government of Japan revised, in May 2015, the basic plan to expand the site selection process, in which a set of site screening criteria was issued based on the existing geoscientific knowledge. These criteria were developed by the Geological Disposal Technology Working Group of the Nuclear Energy Subcommittee which was created by the Ministry of Economy, Trade and Industry (METI). (author)

  14. Life cycle assessment of geological repositories for the final disposal of spent fuel in Finland and Sweden

    International Nuclear Information System (INIS)

    Puhrer, A.; Bauer, C.

    2014-01-01

    This paper presents a Life Cycle Assessment (LCA) of the geological repositories for the final disposal of spent nuclear fuel in Finland and Sweden. A separate LCA has been performed for the geological spent fuel repository in each country and the results have been compared. A further benchmark comparison has been made with the LCA of the Swiss geological repository for high-level waste and spent fuel. The life cycle inventory (LCI) product system boundaries include the spent fuel repository and encapsulation facility in each country. All materials, processes, consumed utilities and transport associated with the construction, operation and closure of the repositories for spent fuel are included in the LCI. The life cycle impact assessment (LCIA) is performed using two methods: IPCC 2007 Climate Change and ReCiPe. These assessment methods return results pertaining to global warming potential (GWP) as well as a number of environmental impact categories such as human toxicity and natural land transformation. Results indicate that the use of copper for disposal canister fabrication and bentonite for repository backfilling are the causes for most of the environmental impact of the spent fuel repositories in Finland and Sweden. Alternate, less bentonite-intensive backfilling scenarios may mitigate this impact. While the Swiss bentonite consumption is lower and no copper is used for canister fabrication, the Swiss electricity and fuel consumption associated with final disposal of high-level waste and spent fuel is significantly higher than in Finland or Sweden. Approximately 1 g CO 2 -eq is emitted due to the final disposal of spent fuel and HLW per kWh of nuclear generated electricity. This represents some 10% of the emissions due to the entire nuclear energy chain and is practically negligible in the context of GHG emissions of other energy technologies. (authors)

  15. The HILW-LL (high- and intermediate-level waste, long-lived) disposal project: working toward building the Cigeo Industrial Centre for Geological Disposal

    International Nuclear Information System (INIS)

    Labalette, Th.

    2011-01-01

    The French Act of 28 June 2006 identifies reversible disposal in deep geological facilities as the benchmark solution for long-term management of high-level waste (HLW) and for intermediate-level long-lived waste (ILW-LL). The Act tasks ANDRA (national agency for the management of radioactive wastes) with the pursuit of studies and research on the choice of a site and the design of the repository, with a view to examining the licence application in 2015 and, provided that the licence is granted, to make the facility operational by 2025. At the end of 2009, ANDRA submitted to the Government its proposals regarding the site and the design of the Industrial Centre for Geological Disposal, known as CIGEO. With the definition of a possible area for the construction of underground disposal facilities, one of the key stages in the project has been achieved. The choice of a surface site will be validated following the public consultation scheduled for the end of 2012. The project is now on the point of entering the definition stage (preliminary design). CIGEO will be a nuclear facility unlike any other. It will be built and operated for a period of over 100 years. For it to be successful, the project must meet certain requirements related to its integration in the local area, industrial planning, safety and reversibility, while also controlling costs. Reversibility is a very important concept that will be defined by law. It is ANDRA's responsibility to ensure that a reasonable balance is found between these different concerns. (author)

  16. 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

  17. The current regulatory requirements on optimisation and BAT in Sweden in the context of geological disposal

    International Nuclear Information System (INIS)

    Dverstorp, B.

    2010-01-01

    Bjorn Dverstorp, Swedish Radiation Safety authority (SSM) presented 'The current regulatory requirements on optimisation and BAT in Sweden in the context of geological disposal'. In Sweden, a nuclear waste repository will be evaluated according to both to general environmental legislation (the Environmental Code, SFS, 1998:808) and according to more specific requirements in the Act on Nuclear Activities (SFS, 1984:3) and the Radiation Protection Act (SFS, 1988:220). The evaluations according to these laws will be carried out according to two separate, but coordinated, legal-review and decision-making processes. This will be a basis for the siting process. Although the requirements on BAT and siting in the Environmental Code apply to radiological protection, they aim at a broader system optimisation. The more specific requirements on optimisation and BAT of radiological protection of geological disposal systems are given in the regulations associated with the Radiation Protection Act. The Swedish radiation protection regulations (SSM, 2009) comprise three corner stones: a risk target, environmental protection goals and the use of optimisation and BAT. In SSM' s guidance optimisation is defined as a means to reduce risk, guided by the results of risk calculations. In case of a conflict between BAT and optimisation, measures satisfying BAT should have priority. Application of optimisation and BAT on different timescales are described as well as for human intrusion scenarios. B. Dverstorp explained that because of uncertainties in the long term there is a need for additional arguments in the safety case in support of decision making. It is in this context that the requirements on optimisation and BAT should be seen as supplementary to the risk target, in providing evidence that the developer has taken into consideration, as far as reasonably possible, measures and options for reducing future doses and risks. Both principles focus on the proponent's work on developing

  18. 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.)

  19. Public attitudes toward geological disposal of carbon dioxide in Canada : final report

    International Nuclear Information System (INIS)

    Sharp, J.

    2005-01-01

    A research project investigating the public's perceptions of the risks and benefits of the geologic disposal of carbon dioxide (GDC) technology was presented. Data for the project was collected in 2 phases. Focus groups were conducted in order to understand the likely range of attitudes and concerns about the technology. The information obtained from the focus groups was then used to design an Internet-based survey for administration to a sample of 1967 Canadians. The survey included questions about climate change and GDC as well as a discrete choice experiment. Linear multiple regression analysis was used to identify the determinants of the respondents' support for GDC. Results showed that while a strong majority of Canadians believed that climate change was occurring, climate change ranked very low in importance compared to other national issues, and was the lowest ranked environmental issue. Knowledge of GDC was low, and the vast majority of those who had heard of GDC could not identify what environmental problem it was meant to address. The most important benefits of GDC were seen to be its utility as a bridging technology while long-term climate change solutions are developed; the potential for its use in enhanced oil recovery; and its ability to reduce greenhouse gas (GHG) emissions. However, the risks of GDC were rated as more important than the benefits, and included concerns about unknown future impacts; contamination of groundwater; the risk of a carbon dioxide (CO 2 ) leak; and risks to plants and animals. It was concluded that respondents were slightly supportive of GDC development in Canada, and perceived the technology as having a net positive impact on the environment. GDC was seen as less risky than normal oil and gas industry operations, nuclear power, or coal-burning power plants. It was concluded that GDC is less popular then energy efficiency and renewable energy alternatives, and should be used in combination with these technologies in order to

  20. Geo-microbiological reactivity of iron materials: impact on geological disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Esnault, L.

    2010-01-01

    This thesis sought to describe the dynamic concept of a viable and sustainable microbiological activity under deep geological disposal conditions and to assess its impact on containment properties and storage components. Thus, in this study, a model based on the bacterial ferric reduction was chosen for its sustainability criteria in the system and its ability to alter the materials in storage conditions. The main results of this work demonstrated the capability of the environment to stand the iron-reducing bacterial activity and the conditions of its development in the deep clay environments. The bio-availability of structural Fe (III) in clay minerals and iron oxides produced during the process of metal corrosion was clearly demonstrated. In this system, the corrosion appears to be a positive factor on bacterial activities by producing an energy source, hydrogen. The iron-reducing bacterial activities can lead to a resumption of metallic corrosion through the consumption of iron oxides in the passive film. The direct consequence would be a reduction of the lifetime of metal containers. In the case of ferric clay minerals, the consequences of such an activity are such that they can have an impact on the overall porous structure both in terms of chemical reactivity of the materials or physical behavior of the clayey barrier. One of the most significant results is the crystallization of new clay phases at very low temperatures, below 40 C, highlighting the influence of the anaerobic microbial activity in the mineralogical transformations of clay minerals. Furthermore, these experiments also allowed to visualize, for the first time, a mechanism of bacterial respiration at distance, this increases the field of the availability of essential elements as Fe 3+ for bacterial growth in extreme environment. In conclusion, these results clearly showed the impact of the microbiological factor on the reactivity of clay and metal minerals, while relying on control parameters on

  1. Methodology of fuel cycles long-term safety assessment of SNF/HLW geological disposal

    International Nuclear Information System (INIS)

    Pritrsky, J.

    2008-02-01

    Methodology for the long-term safety assessment of nuclear fuel cycles is given in the presented doctoral thesis. The aim of work was to develop a geological repository model for disposal of spent nuclear fuel (SNF) and high level waste (HLW) using an appropriate software code able to calculate the influence of partitioning and transmutation in advanced fuel cycles. The first step in this process was specifying of indicators which can be used to quantify the radiological impact of each fuel cycle. Indicators such as annual effective dose and radiotoxicity of inventory have been quantitatively analysed to determine the potential risk and radiological consequences associated with production of SNF/HLW. Advanced fuel types bring a number of advantages in comparison to uranium oxide fuel UO 2 used worldwide nowadays in terms of safety improvement due to minor actinides transmutation and non-proliferation aspects as well. Within the scope of work, three different fuel cycles are compared from the point of view of long-term safety of deep geological repository. The first considered fuel cycle is the currently used open fuel cycle (UOX) which uses only U-FA (Uranium Fuel Assembly). The second assessed cycle is a closed fuel cycle (MOX) with MOX-FA (Mixed OXides Fuel Assembly) and the third considered one is a partially closed fuel cycle (IMF) with IMC-FA (Inert Matrix Combined Fuel Assembly). Description and input data of advanced fuel cycles have been gained by participation in the EC project RED-IMPACT. Results were calculated using code AMBER, which is a flexible software tool that allows building dynamic compartmental models to represent the migration and fate of contaminants in a system, for example in the surface and sub-surface environment. Contaminants in solid, liquid and gaseous phases can be considered. AMBER gives the user the flexibility to define any number of compartments; any number of contaminants and associated decays; deterministic, probabilistic and

  2. Methodology of fuel cycles long-term safety assessment of SNF/HLW geological disposal

    International Nuclear Information System (INIS)

    Pritrsky, J.

    2008-01-01

    Methodology for the long-term safety assessment of nuclear fuel cycles is given in the presented doctoral thesis. The aim of work was to develop a geological repository model for disposal of spent nuclear fuel (SNF) and high level waste (HLW) using an appropriate software code able to calculate the influence of partitioning and transmutation in advanced fuel cycles. The first step in this process was specifying of indicators which can be used to quantify the radiological impact of each fuel cycle. Indicators such as annual effective dose and radiotoxicity of inventory have been quantitatively analysed to determine the potential risk and radiological consequences associated with production of SNF/HLW. Advanced fuel types bring a number of advantages in comparison to uranium oxide fuel UO 2 used worldwide nowadays in terms of safety improvement due to minor actinides transmutation and non-proliferation aspects as well. Within the scope of work, three different fuel cycles are compared from the point of view of long-term safety of deep geological repository. The first considered fuel cycle is the currently used open fuel cycle (UOX) which uses only U-FA (Uranium Fuel Assembly). The second assessed cycle is a closed fuel cycle (MOX) with MOX-FA (Mixed OXides Fuel Assembly) and the third considered one is a partially closed fuel cycle (IMF) with IMC-FA (Inert Matrix Combined Fuel Assembly). Description and input data of advanced fuel cycles have been gained by participation in the EC project RED-IMPACT. Results were calculated using code AMBER, which is a flexible software tool that allows building dynamic compartmental models to represent the migration and fate of contaminants in a system, for example in the surface and sub-surface environment. Contaminants in solid, liquid and gaseous phases can be considered. AMBER gives the user the flexibility to define any number of compartments; any number of contaminants and associated decays; deterministic, probabilistic and

  3. Developments in the Canadian program for geological disposal of nuclear fuel waste

    International Nuclear Information System (INIS)

    Allan, C.J.; Nuttall, K.

    1996-01-01

    The Canadian Nuclear Fuel Waste Management Program is at the end of disposal concept and technology development and is now undergoing a comprehensive environmental review. This paper will review: the history of the Canadian program; the disposal concept and the associated technologies; the program achievements and the lessons learned; and the status of the environmental review. (author)

  4. Behavior of rare earth elements in fractured aquifers: an application to geological disposal criteria for radioactive waste

    International Nuclear Information System (INIS)

    Lee, Seung Gu; Kim, Yong Je; Lee, Kil Yong; Kim, Kun Han

    2003-01-01

    An understanding of the geochemistry of potential host rocks is very important in the site evaluation for construction of an underground geologic repository for radioactive waste. Because of similar valence and ionic radii and high similarity in electronic structure with trivalent actinides (such as Am 3+ and Cm 3+ ), the rare earth elements (REEs) have been used to predict the behavior of actinide-series elements in solution (Runde et al., 1992). For Am and Cm, which occur only in the trivalent states in most waste-disposal repository environments, the analogy with the REEs is particularly relevant. In order to discuss the behavior of REEs in geological media and to deduce the behavior of actinides in geological environments based on the REE abundance, and to provide an useful tool in deciding an optimum geological condition for radioactive disposal, we estimated the REE abundance from various kinds of fractured rock type. In fractured granitic aquifer, chondrite-normalized REE pattern show Eu positive anomaly due to fracture-filling calcite precipitation. However, in fractured meta-basaltic and volcanic tuffaceous aquifer, REE pattern do not show the change of Eu anomaly due to fracture-filling calcite precipitation. Eu shows very similar properties such as cohesive energy, ionic radii with coordination number compared to Am. Therefore, if we consider the Eu behavior in fractured rocks and the similar physical/chemical properties of Eu and Am, together, our results strongly suggest that Eu is a very useful analogue for predicting the behavior of Am in geological environment

  5. Operational safety of geological disposal: IRSN project 'EXREV' for developing a safety assessment strategy for the operation and reversibility of a geological repository

    International Nuclear Information System (INIS)

    Tichauer, M.; Pellegrini, D.; Serres, C.; Besnus, F.

    2014-01-01

    A high-level waste geological disposal facility is envisioned by the legislator in the French Planning Act no. 2006-739 of 28 June 2006. This act sets major milestones for the operator (Andra) in 2013 (public debate), 2015 (licensing) and 2025 (operation). In the framework of the regulatory review process, IRSN's mission is to conduct an assessment of the safety case provided by Andra at every stage of the process for the French regulator, namely the Nuclear Safety Authority (ASN). In 2005, IRSN gathered more than twenty years of research and expertise in order to provide a comprehensive appraisal of the 'Dossier 2005' prepared by Andra, related to the feasibility of a geological disposal in the Callovo-Oxfordian clay formation. At this time, the description of the operational phase was only at a preliminary stage, but this step paved the way for developing an assessment strategy of the operational phase. In this perspective, IRSN set up the EXREV project in 2008 in order to build up a doctrine and to identify key safety issues to be dealt with. (authors)

  6. 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

  7. Implications of safety requirements for the treatment of THMC processes in geological disposal systems for radioactive waste

    Directory of Open Access Journals (Sweden)

    Frédéric Bernier

    2017-06-01

    Full Text Available The mission of nuclear safety authorities in national radioactive waste disposal programmes is to ensure that people and the environment are protected against the hazards of ionising radiations emitted by the waste. It implies the establishment of safety requirements and the oversight of the activities of the waste management organisation in charge of implementing the programme. In Belgium, the safety requirements for geological disposal rest on the following principles: defence-in-depth, demonstrability and the radiation protection principles elaborated by the International Commission on Radiological Protection (ICRP. Applying these principles requires notably an appropriate identification and characterisation of the processes upon which the safety functions fulfilled by the disposal system rely and of the processes that may affect the system performance. Therefore, research and development (R&D on safety-relevant thermo-hydro-mechanical-chemical (THMC issues is important to build confidence in the safety assessment. This paper points out the key THMC processes that might influence radionuclide transport in a disposal system and its surrounding environment, considering the dynamic nature of these processes. Their nature and significance are expected to change according to prevailing internal and external conditions, which evolve from the repository construction phase to the whole heating–cooling cycle of decaying waste after closure. As these processes have a potential impact on safety, it is essential to identify and to understand them properly when developing a disposal concept to ensure compliance with relevant safety requirements. In particular, the investigation of THMC processes is needed to manage uncertainties. This includes the identification and characterisation of uncertainties as well as for the understanding of their safety-relevance. R&D may also be necessary to reduce uncertainties of which the magnitude does not allow

  8. 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)

  9. 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

  10. Sectoral Plan 'Deep Geological Disposal', Stage 2. Proposed site areas for the surface facilities of the deep geological repositories as well as for their access infrastructure. Annexes

    International Nuclear Information System (INIS)

    2011-12-01

    In line with the provisions of the nuclear energy legislation, the sites for deep geological disposal of Swiss radioactive waste are selected in a three-stage Sectoral Plan process (Sectoral Plan for Deep Geological Disposal). The disposal sites are specified in Stage 3 of the selection process with the granting of a general licence in accordance with the Nuclear Energy Act. The first stage of the process was completed on 30 th November 2011, with the decision of the Federal Council to incorporate the six geological siting regions proposed by the National Cooperative for the Disposal of Radioactive Waste (NAGRA) into the Sectoral Plan for Deep Geological Disposal, for further evaluation in Stage 2. The decision also specifies the planning perimeters within which the surface facilities and shaft locations for the repositories will be constructed. In the second stage of the process, at least two geological siting regions each will be specified for the repository for low- and intermediate-level waste (L/ILW) and for the high-level waste (HLW) repository and these will undergo detailed geological investigation in Stage 3. For each of these potential siting regions, at least one location for the surface facility and a corridor for the access infrastructure will also be specified. NAGRA is responsible, at the beginning of Stage 2, for submitting proposals for potential locations for the surface facilities and their access infrastructure to the Federal Office of Energy (SFOE); these are then considered by the regional participation bodies in the siting regions. The general report and the present annexes volume document these proposals. In Stage 2, under the lead of the SFOE, socio-economic-ecological studies will also be carried out to investigate the impact of a repository project on the environment, economy and society. The present reports also contain the input data to be provided by NAGRA for the generic (site-independent) part of these impact studies. A meaningful

  11. Sectoral Plan 'Deep Geological Disposal', Stage 2. Proposed site areas for the surface facilities of the deep geological repositories as well as for their access infrastructure. General report

    International Nuclear Information System (INIS)

    2011-12-01

    In line with the provisions of the nuclear energy legislation, the sites for deep geological disposal of Swiss radioactive waste are selected in a three-stage Sectoral Plan process (Sectoral Plan for Deep Geological Disposal). The disposal sites are specified in Stage 3 of the selection process with the granting of a general licence in accordance with the Nuclear Energy Act. The first stage of the process was completed on 30 th November 2011, with the decision of the Federal Council to incorporate the six geological siting regions proposed by the National Cooperative for the Disposal of Radioactive Waste (NAGRA) into the Sectoral Plan for Deep Geological Disposal, for further evaluation in Stage 2. The decision also specifies the planning perimeters within which the surface facilities and shaft locations for the repositories will be constructed. In the second stage of the process, at least two geological siting regions each will be specified for the repository for low- and intermediate-level waste (L/ILW) and for the high-level waste (HLW) repository and these will undergo detailed geological investigation in Stage 3. For each of these potential siting regions, at least one location for the surface facility and a corridor for the access infrastructure will also be specified. NAGRA is responsible, at the beginning of Stage 2, for submitting proposals for potential locations for the surface facilities and their access infrastructure to the Federal Office of Energy (SFOE); these are then considered by the regional participation bodies in the siting regions. The present report and its annexes volume document these proposals. In Stage 2, under the lead of the SFOE, socio-economic-ecological studies will also be carried out to investigate the impact of a repository project on the environment, economy and society. The present reports also contain the input data to be provided by NAGRA for the generic (site-independent) part of these impact studies. A meaningful discussion

  12. Implications of monitored retrievable storage for geologic disposal of spent nuclear fuel and high level radioactive waste

    International Nuclear Information System (INIS)

    Halstead, R.J.; Kidwell, S.M.; Woodbury, D.

    1986-01-01

    The integral monitored retrievable storage (I-MRS) proposal has major implications for geologic disposal. This paper reviews the positive and negative implications from the standpoint of a potential repository host state. Recommendations for improving the I-MRS proposal include: eliminate provisions restricting I-MRS backup role; add provisions to prevent I-MRS from becoming a permanent disposal facility; optimize reactor-to-I-MRS transportation system; further shift preclosure operations from repository to I-MRS; defer decision on rod consolidation; repeat the I-MRS site selection process; eliminate any potential linkage between I-MRS and nuclear weapons programs; and incorporate I-MRS in the repository siting program

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  14. Investigation on CO2 property and its geological disposal in coal bed

    International Nuclear Information System (INIS)

    Liang Weiguo; Wu Di; Hao Shuping

    2008-01-01

    Carbon dioxide is main green house gas, and it has been increased greatly in the atmosphere since the industrial revolution. The human living environment has been worsened with more and more carbon dioxide in the air. In this paper, the authors analyzed the physical property of carbon dioxide and green house gas effect, then studied the disposal measures for carbon dioxide. At last it was pointed out that various measures should be taken to carry out the carbon dioxide disposal, more economic benefit can be anticipated along with carbon dioxide disposal by EOR, CO 2 -ECBM, CAES, et al, of which CO 2 -ECBM is one of the way with best benefits. (authors)

  15. A design concept of underground facilities for the deep geologic disposal of spent fuel

    International Nuclear Information System (INIS)

    Lee, Jong Youl; Choi, Heui Joo; Choi, Jong Won; Hahn, Pil Soo

    2005-01-01

    Spent nuclear fuel from nuclear power plants can be disposed in the underground repository. In this paper, a concept of Korean Reference HLW disposal System (KRS-1) design is presented. Though no site for the underground repository has been specified in Korea, but a generic site with granitic rock is considered for reference spent fuel repository design. To implement the concept, design requirements such as spent fuel characteristics and capacity of the repository and design principles were established. Then, based on these requirements and principles, a concept of the disposal process, the facilities and the layout of the repository was developed

  16. Use of in-vitro experimental results to model in-situ experiments: bio-denitrification under geological disposal conditions.

    Science.gov (United States)

    Masuda, Kaoru; Murakami, Hiroshi; Kurimoto, Yoshitaka; Kato, Osamu; Kato, Ko; Honda, Akira

    2013-01-01

    Some of the low level radioactive wastes from reprocessing of spent nuclear fuels contain nitrates. Nitrates can be present in the form of soluble salts and can be reduced by various reactions. Among them, reduction by metal compounds and microorganisms seems to be important in the underground repository. Reduction by microorganism is more important in near field area than inside the repository because high pH and extremely high salt concentration would prevent microorganism activities. In the near field, pH is more moderate (pH is around 8) and salt concentration is lower. However, the electron donor may be limited there and it might be the control factor for microorganism's denitrification activities. In this study, in-vitro experiments of the nitrate reduction reaction were conducted using model organic materials purported to exist in underground conditions relevant to geological disposal. Two kinds of organic materials were selected. A super plasticizer was selected as being representative of the geological disposal system and humic acid was selected as being representative of pre-existing organic materials in the bedrock. Nitrates were reduced almost to N2 gas in the existence of super plasticizer. In the case of humic acids, although nitrates were reduced, the rate was much lower and, in this case, dead organism was used as an electron donor instead of humic acids. A reaction model was developed based on the in-vitro experiments and verified by running simulations against data obtained from in-situ experiments using actual groundwaters and microorganisms. The simulation showed a good correlation with the experimental data and contributes to the understanding of microbially mediated denitrification in geological disposal systems.

  17. 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

  18. Regulation and Guidance for the Geological Disposal of Radioactive Waste. Review of the Literature and Initiatives of the Past Decade

    International Nuclear Information System (INIS)

    2010-01-01

    In January 1997, the NEA workshop 'Regulating the Long-term Safety of Radioactive Waste Disposal' (the 'Cordoba workshop') provided an important reference point for regulatory issues in the field of geological disposal of radioactive waste. These issues included regulatory frameworks at the national and international levels, the understanding of what is meant by demonstrating regulatory compliance, and approaches to an appropriate regulatory process. In the intervening years many international and national developments have taken place. A follow-up workshop was organised in Tokyo in January 2009 to take stock of progress, with a draft providing an overview of the development of regulation and guidance at both national and international levels, on international and multi-national initiatives for developing recommendations and common views on regulatory issues, as well as an overview of the experience of regulatory review of some of the safety studies produced during the last decade. This paper reviews the evolution of these initiatives and issues over the past decade or so focusing on the major areas addressed in Cordoba, notably: international developments in regulation (IRCP recommendations, IAEA Safety Standards, developments at the NEA), radioactive waste disposal criteria (risk/dose criteria for protection of human beings, protection of the environment, timescales), performance assessment trends (General development of performance assessment/safety case, further technical, scientific and methodical aspects), the conduct of the regulatory process (technical review process, non-technical aspects and their impact). With regard to regulatory development at the international level, the Safety Requirements WS-R-4 'Geological Disposal of Radioactive Waste' (issued in 2006 and jointly sponsored by the IAEA and the NEA) is addressed in particular

  19. Development of an engineering design process and associated systems and procedures for a UK geological disposal facility - 59160

    International Nuclear Information System (INIS)

    Rendell, Philip; Breen, Brendan; Clark, Alastair; Reece, Steve; O'Grady, Henry

    2012-01-01

    In the United Kingdom the Nuclear Decommissioning Authority (NDA) has been charged with implementing Government policy for the long-term management of higher activity radioactive waste. The UK Government is leading a site selection process based on voluntarism and partnership with local communities interested in hosting such a facility and as set out in the 'Managing Radioactive Waste Safely' White Paper (2008). The NDA has set up the Radioactive Waste Management Directorate (RWMD) as the body responsible for planning, building and operating a geological disposal facility (GDF). RWMD will develop into a separately regulated Site Licence Company (SLC) responsible for the construction, operation and closure of the facility. RWMD will be the Design Authority for the GDF; requiring a formal process to ensure that the knowledge and integrity of the design is maintained. In 2010 RWMD published 'Geological Disposal - Steps towards implementation' which described the preparatory work that it is undertaking in planning the future work programme, and the phases of work needed to deliver the programme. RWMD has now developed a process for the design of the GDF to support this work. The engineering design process follows a staged approach, encompassing options development, requirements definition, and conceptual and detailed designs. Each stage finishes with a 'stage gate' comprising a technical review and a specific set of engineering deliverables. The process is intended to facilitate the development of the most appropriate design of GDF, and to support the higher level needs of both the project and the community engagement programmes. The process incorporates elements of good practices derived from other work programmes; including process mapping, issues and requirements management, and progressive design assurance. A set of design principles have been established, and supporting design guidance notes are being produced. In addition a requirements management system is being

  20. Radiation damage studies on natural rock salt from various geological localities of interest to the radioactive waste disposal program

    International Nuclear Information System (INIS)

    Levy, P.W.

    1981-01-01

    As part of a program to investigate radiation damage in geological materials of interest to the radioactive waste disposal program, radiation damage, particularly radiation induced sodium metal colloid formation, has been studied in 14 natural rock salt samples. All measurements were made with equipment for making optical absorption and other measurements on samples, in a temperature controlled irradiation chamber, during and after 0.5 to 3.0 MeV electron irradiation. Samples were chosen for practical and scientific purposes, from localities that are potential repository sites and from different horizons at certain localities

  1. Great Meteor East (distal Madeira Abyssal Plain): geological studies of its suitability for disposal of heat-emitting radioactive wastes

    International Nuclear Information System (INIS)

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

    1985-01-01

    This report summarises geological and geophysical studies carried out by the Institute of Oceanographic Sciences up to December 1983 in an area of the Madeira Abyssal Plain in order to assess its suitability for the disposal of heat-emitting radioactive waste. The results of work carried out in the same area by the Rijks Geologische Dienst of the Netherlands are also reviewed in the report. Other oceanographic studies in the area in the fields of geochemistry, biology and oceanography are briefly touched upon. (author)

  2. Suggestions on selection of clay site as a key alternative of underground repository for HLW geological disposal in China

    International Nuclear Information System (INIS)

    Zheng Hualing; Fu Bingjun; Fan Xianhua; Chen Shi; Sun Donghui

    2006-01-01

    Site selection for the underground repository is a vital problem with respect to the HLW geological disposal. Over the past decades, we have been focusing our attention on granite as a priority in China. However, there are some problems have to be discussed on this matter. In this paper, both experiences gained and lessons learned in the international community regarding the site selection are described. And then, after analyzing a lot of some key factors affecting the site selection, some comments and suggestions on selection of clay site as a key alternative before final decision making in China are presented. (authors)

  3. Prediction of geological and mechanical processes while disposing of high-level waste (HLW) into the earth crust

    International Nuclear Information System (INIS)

    Kedrovsky, O.L.; Morozov, V.N.

    1992-01-01

    Prediction of geological and mechanical processes while disposing of high-level waste of atomic industry into the earth crust is the fundamental base for ecological risk assessment (possible consequences) while developing repository designs. The subject of this paper is the analytical estimate of possibilities of rock fracturing mechanisms to predict isolation properties loss by massif beginning from crystal lattice of minerals up to large fracture disturbances under conditions of long-term influence of pressure, temperature, and radiation. To solve the problem possibilities of kinetic

  4. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  5. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    International Nuclear Information System (INIS)

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules

  6. 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)

  7. Report of the second meeting of the consultants on coupled processes associated with geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    Tsang, Chin-Fu; Mangold, D.C.

    1985-09-01

    The second meeting of the Consultants on Coupled Processes Associated with Geological Disposal of Nuclear Waste occurred on January 15-16, 1985 at Lawrence Berkeley Laboratory (LBL). All the consultants were present except Dr. K. Kovari, who presented comments in writing afterward. This report contains a brief summary of the presentations and discussions from the meeting. The main points of the speakers' topics are briefly summarized in the report. Some points that emerged during the discussions of the presentations are included in the text related to the respective talks. These comments are grouped under the headings: Comments on Coupled Processes in Unsaturated Fractured Porous Media, Comments on Overview of Coupled Processes, Presentations by Consultants on Selected Topics of Current Interest in Coupled Processes, and Recommendations for Underground Field Tests with Applications to Three Geologic Environments

  8. Use of natural and archaeological analogs to validate long - term behaviour of HLW glass in geological disposal conditions

    International Nuclear Information System (INIS)

    Gin, S.; Verney-Carron, A.; Libourel, G.

    2008-01-01

    Some old basaltic and Roman glasses have been studied in order to validate the predictive models developed for assessing the long-term behaviour of nuclear glass in geological repository conditions. Leaching behaviour of basaltic glass altered in both laboratory and natural environment conditions allows to validate the key mechanisms that control glass dissolution kinetics and the order of magnitude of glass packages lifetime In a stable clayey formation (French reference concept for a geological disposal of high level waste). The study of Roman glass blocks (with the same geometry as nuclear glass package) altered during 1800 years in a marine environment gives new insight on the basic mechanisms involved in confined media (fractures and small cracks). Results show the importance of the coupling between transport of reactive species and chemical reactions. This study, still in progress, would allow to validate the modelling of such a complex system. (author)

  9. 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)

  10. 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)

  11. 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

  12. 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.)

  13. Evaluation of long-term interaction between cement and bentonite for geological disposal (1) - Project Overview

    International Nuclear Information System (INIS)

    Owada, Hitoshi; Hayashi, Daisuke; Yahagi, Ryoji; Ishii, Tomoko

    2012-01-01

    Document available in extended abstract form only. Bentonitic and cementitious materials are both planned for use as engineered barrier materials in the geological disposal of high level vitrified waste and TRU (transuranic) waste in Japan. As shown in Figure 1, bentonitic material will be placed around the waste packages as buffer material and a large amount of cementitious material is specified for use as filler, structure, support and grout. Cementitious material supplies an alkaline solution with high calcium concentration through reaction with groundwater. However, the alkaline solution will cause chemical and physical alteration of the bentonitic material. Since many important functions of an engineered barrier system (EBS), such as watertightness, chemical buffering, and sorption of radioactive nuclides, will be maintained by the properties of the buffer material, evaluation of long-term chemical or mechanical alteration of the buffer material is necessary to demonstrate the robustness of the EBS. Although many researches on chemical and mechanical alteration of bentonitic material, there was large uncertainty because the chemical alteration of bentonitic material is very slow and the altered region is very limited. In this project, the dissolution rate of montmorillonite under compaction and the spatial distribution of secondary C-S-H precipitation were obtained and mechanical and hydrological changes caused by the mineralogical change of bentonite material were modeled to reduce the uncertainty in the safety assessment of EBS performance. To improve the accuracy of the long term evaluation of the EBS performance, coupled analyses between hydraulic/mechanical calculations and geochemical-mass transport coupled calculations were performed. Alteration of mechanical properties caused by chemical degradation should be modeled for the coupled calculations. Because the mechanical properties of bentonitic material depend strongly on the montmorillonite content and

  14. Trip report: workshop on risk analysis and geologic modeling in relation to the disposal of radioactive wastes into geological formations

    International Nuclear Information System (INIS)

    Claiborne, H.C.

    1977-01-01

    The Workshop was co-sponsored by the Commission of European Communities (CEC) and the Office of Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA), with primary object being to promote international cooperation in developing and using risk assessment techniques for the long-term safety assessment of waste disposal. The attendance was restricted to specialists in the field and a few observers; 43 people were in attendance representing 14 different countries. Nothing particularly new or novel was presented nor any formal cooperation agreed upon. However, there was a feeling that continued informal cooperation was helpful and should be continued. Greater or lesser degrees of formality could be decided later. The U.S. program was definitely more advanced and larger in scope than the others that were discussed. Countries that seemed to have significant programs include the Federal Republic of Germany, France, Canada, Sweden, and the CEC. Abstracts of papers are presented together with consensus reports on containment failure modes and geosphere transport modeling

  15. Microbes in deep geological systems and their possible influence on radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    West, J M; McKinley, I G; Chapman, N A [Institute of Geological Sciences, Harwell (UK). Environmental Protection Unit

    1982-09-01

    Although the fact is often overlooked, proposed nuclear waste repositories in geological formations would exist in an environment quite capable of sustaining microbial life which could considerably affect containment of radionuclides. In this paper a brief review of biological tolerance of extreme environments is presented with particular reference to studies of the microbiology of deep geological formations. The possible influence of such organisms on the integrity of a waste repository and subsequent transport of radionuclides to the surface is discussed.

  16. RD and D steering of a geological disposal programme in poorly indurated clays - ONDRAF/NIRAS example

    International Nuclear Information System (INIS)

    Van Geet, M.; Capouet, M.; Depaus, C.; Lalieux, P.

    2012-01-01

    Document available in extended abstract form only. For more than thirty years, Belgium has been investigating clay formations for its potential suitability to host a geological disposal. The R and D programme initiated as early as 1974 by the Belgian Nuclear Research Centre (SCK.CEN) at Mol was pursued from the early 1980's under ONDRAF/NIRAS' responsibility. These studies quickly focused on the Boom Clay formation at Mol-Dessel, in northeastern Belgium, as a potential host formation for a geological repository. The state of scientific and technical research on the possible disposal of high-and intermediate level radioactive waste (B and C waste) in clay layers was presented in decanal safety assessment reports and internationally reviewed. Over time, geological disposal in Boom Clay has progressively become the reference solution of ONDRAF/NIRAS for the long-term management of category B and C wastes, geological disposal in Ypresian Clays being considered as an alternative solution. The national and international peer review of the second Safety and Feasibility interim report (SAFIR 2) acknowledged in 2001 the maturity of the Belgian scientific program and endorsed ONDRAF/NIRAS conclusion to pursue the RD and D program on poorly indurated clays. Consequently, the NEA International Review Team urged ONDRAF/NIRAS to move on to the implementation phase while pursuing RD and D necessary to reduce the remaining uncertainties. This major step required ONDRAF/NIRAS to develop the frame and tools to embed its national program in a societal dialogue and in a stepwise decision-making plan with key milestones stretching over the next decades towards the licensing process. To serve these ends, ONDRAF/NIRAS has reassessed the organization of its geological disposal program. A strategy had to be set out to frame and formalize the stepwise and iterative development of a geological disposal in a coherent and integrating manner. Indeed, firstly, the maturity of the program had led

  17. 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)

  18. Annotated bibliography for the design of waste packages for geologic disposal of spent fuel and high-level waste

    International Nuclear Information System (INIS)

    Wurm, K.J.; Miller, N.E.

    1982-11-01

    This bibliography identifies documents that are pertinent to the design of waste packages for geologic disposal of nuclear waste. The bibliography is divided into fourteen subject categories so that anyone wishing to review the subject of leaching, for example, can turn to the leaching section and review the abstracts of reports which are concerned primarily with leaching. Abstracts are also cross referenced according to secondary subject matter so that one can get a complete list of abstracts for any of the fourteen subject categories. All documents which by their title alone appear to deal with the design of waste packages for the geologic disposal of spent fuel or high-level waste were obtained and reviewed. Only those documents which truly appear to be of interest to a waste package designer were abstracted. The documents not abstracted are listed in a separate section. There was no beginning date for consideration of a document for review. About 1100 documents were reviewed and about 450 documents were abstracted

  19. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    International Nuclear Information System (INIS)

    1982-03-01

    The NWTS-33 series, of which this document is a part, provides guidance for the National Waste Terminal Storage (NWTS) program in the development and implementation of licensed mined geologic disposal systems for solidified high-level and TRU wastes. Program objectives, functional requirements, and system performance criteria are found in this document. At the present time final criteria have not been issued by the Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA). The criteria in these documents have been developed on the basis of DOE's judgment of what is required to protect the health and safety of the public and the quality of the environment. It is expected that these criteria will be consistent with regulatory standards. The criteria will be re-evaluated on a periodic basis to ensure that they remain consistent with national waste management policy and regulatory requirements. A re-evaluation will be made when final criteria are promulgated by the NRC and EPA. A background section that briefly describes the mined geologic disposal system and explains the hierarchy and application of the NWTS criteria is included in Section 2.0. Secton 3.0 presents the program objectives, Section 4.0 functional requirements, Secton 5.0 the system performance criteria, and Section 6.0 quality assurance and standards. A draft of this document was issued for public comment in April 1981. Appendix A contains the DOE responses to the comments received. Appendix B is a glossary

  20. Development of site selection criteria for radioactive waste disposal in view of favourable geological settings in Germany

    International Nuclear Information System (INIS)

    Baltes, B.; Brewitz, W.

    2001-01-01

    In Germany it is intended to dispose of all types of radioactive waste in deep geological formations. Since the government has doubts regarding the suitability of the Gorleben site, further sites in different host rock formations have to be investigated. This investigation process has to be carried out with respect to technical suitability and safety as well as to public acceptance. A Committee has been established whose mandate is to develop a comprehensible procedure for the selection of sites for radioactive waste disposal in Germany. The Committee developed an iterative procedure which provides, besides the increase of transparency, the necessary flexibility in dealing with assessment results. The method is governed by geo-scientific and social-scientific criteria that are presented in this paper. 7 steps have been identified in the procedure: 1) exclusion of areas with obviously unfavourable conditions, 2) identification of areas with favourable geological settings, 3) exclusion of areas for socio-scientific reasons, 4) identification of regions with favourable conditions and ranking of regions, 5) identification of sites for further identification, 6) above-ground site investigation and ranking of potentially suitable sites, and 7) identification of sites for suitability investigations. The first 3 steps give the remaining areas that meet the minimum requirements. The criteria of the first 3 steps are: extensive vertical movements, active disturbance zones, seismic activity and volcanic activity, as for the 4 last steps criteria are based on geo- and socio- scientific weighing, voluntariness and regional mediation. (A.C.)

  1. 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)

  2. Development of site selection criteria for radioactive waste disposal in view of favourable geological settings in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Baltes, B.; Brewitz, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Cologne (Germany)

    2001-07-01

    In Germany it is intended to dispose of all types of radioactive waste in deep geological formations. Since the government has doubts regarding the suitability of the Gorleben site, further sites in different host rock formations have to be investigated. This investigation process has to be carried out with respect to technical suitability and safety as well as to public acceptance. A Committee has been established whose mandate is to develop a comprehensible procedure for the selection of sites for radioactive waste disposal in Germany. The Committee developed an iterative procedure which provides, besides the increase of transparency, the necessary flexibility in dealing with assessment results. The method is governed by geo-scientific and social-scientific criteria that are presented in this paper. 7 steps have been identified in the procedure: 1) exclusion of areas with obviously unfavourable conditions, 2) identification of areas with favourable geological settings, 3) exclusion of areas for socio-scientific reasons, 4) identification of regions with favourable conditions and ranking of regions, 5) identification of sites for further identification, 6) above-ground site investigation and ranking of potentially suitable sites, and 7) identification of sites for suitability investigations. The first 3 steps give the remaining areas that meet the minimum requirements. The criteria of the first 3 steps are: extensive vertical movements, active disturbance zones, seismic activity and volcanic activity, as for the 4 last steps criteria are based on geo- and socio- scientific weighing, voluntariness and regional mediation. (A.C.)

  3. The new ICRP recommendations on radiological protection in geological disposal of long-lived solid radioactive waste

    International Nuclear Information System (INIS)

    Lochard, Jacques; Schneider, Thierry

    2014-01-01

    Radioactive waste management has been the subject of several recommendations of the International Commission on Radiological Protection (ICRP) since 1985. The aim of the new Publication 122 (2013) is to describe how the 2007 general recommendations of the Commission (Publication 103) can be applied in the context of geological disposal. For this purpose, it is important to emphasise that the new approach developed by ICRP is based on three types of exposure situations: planned, emergency and existing: - Planned exposure situations correspond to situations where exposures result from the operation of deliberately introduced sources. Exposures can be planned and fully controlled. - Emergency exposure situations correspond to situations where exposures result from the loss of control of a source within a planned exposure, or from an unexpected situation (e.g. malevolent event). These situations require urgent actions to prevent or mitigate exposures. - Existing exposure situations correspond to situations where exposures result from sources that already exist when decisions are taken to control them. The characterisation of exposure is therefore a prerequisite for their control. The application of the three basic radiological protection principles - justification, optimisation of protection and limitation of individual doses - are therefore considered in this new framework with justification and optimisation applying to the three types of exposure situations and limitation only to planned exposure situations. The main points highlighted in Publication 122 for the application of the system of radiological protection to geological disposal of long-life solid radioactive waste are summarized

  4. A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

    Energy Technology Data Exchange (ETDEWEB)

    Sevougian, S. David [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); MacKinnon, Robert J. [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Leigh, Christi D. [Defense Waste Management Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Hansen, Frank D. [Geoscience Research and Applications Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States)

    2013-07-01

    The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

  5. A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

    International Nuclear Information System (INIS)

    Sevougian, S. David; MacKinnon, Robert J.; Leigh, Christi D.; Hansen, Frank D.

    2013-01-01

    The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

  6. 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)

  7. 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)

  8. Open of chat rooms for discussing geological disposal issues and review of adequate approaches for offering the information using the internet

    International Nuclear Information System (INIS)

    Takizawa, Masayuki; Ito, Toshikazu; Yabuta, Naohiro; Yoshizawa, Nobuaki; Tsunoda, Hirokazu

    2001-03-01

    JNC is doing publicity work to let the technical reliability for geological disposal of high-level radioactive waste (HLW) comprehended widely. But the information about geological disposal of HLW itself and its technology has not been spread and recognized. It has been required to offer the opportunity to discuss the geological disposal and its technology as our own issue. Recently the internet, which has such characteristics as two-way, instant and open communication means, has become used on business and for pleasure commonly. So the opportunity for discussing the topics related to geological disposal of HLW has been offered on the internet web site so-called 'Internet Forum' by JNC since fiscal year 1999. 'Internet Forum' or an assembly of chat rooms is being run on the web server which is not operated by JNC in order to provide the place where discussion on the issue can be done as fairly and objectively as possible. In this report, the results of Internet Forum in fiscal year 2000 comparing with that in fiscal year 1999 were shown and the adequate approaches of operating 'Internet Forum' and offering the information about geological disposal of HLW were reviewed. (author)

  9. 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)

  10. 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)

  11. Issues relating to safety standards on the geological disposal of radioactive waste. Proceedings of a specialists meeting

    International Nuclear Information System (INIS)

    2002-06-01

    Within the International Atomic Energy Agency focus is currently being placed on establishing safety standards for the geological disposal of radioactive waste. This is a challenging task and a Specialists Meeting was held from 18 to 22 June 2001 with the intention of providing a mechanism for promoting discussion on some of the associated scientific and technical issues and as a means of developing the consensus needed for establishing the standards. The meeting used, as its basis, a number of position papers developed in recent years with the help of a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, together with selected relevant regional and national papers. The report contains the summaries of the sessions of the Specialists Meeting together with the conclusions drawn relevant to the establishment of standards. The sessions of the Meeting addressed the following topics: Common framework for radioactive waste disposal; Making the safety case - demonstrating compliance; Safety indicators; Reference critical groups and biospheres; Human intrusion; Reversibility and retrievability; Monitoring and institutional control. The publication contains 26 individual presentations delivered by participants. Each of these presentations was indexed separately

  12. 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)

  13. Study of (U,Pu)O2 spent fuel matrix alteration under geological disposal conditions: Experimental approach and geochemical modeling

    International Nuclear Information System (INIS)

    Odorowski, Melina

    2015-01-01

    To assess the performance of direct disposal of spent fuel in a nuclear waste repository, researches are performed on the long-term behavior of spent fuel (UO x and MO x ) under environmental conditions close to those of the French disposal site. The objective of this study is to determine whether the geochemistry of the Callovian-Oxfordian (CO x ) clay geological formation and the steel overpack corrosion (producing iron and hydrogen) have an impact on the oxidative dissolution of the (U,Pu)O 2 matrix under alpha radiolysis of water. Leaching experiments have been performed with UO 2 pellets doped with alpha emitters (Pu) and MIMAS MO x fuel (un-irradiated or spent fuel) to study the effect of the CO x groundwater and of the presence of metallic iron upon the oxidative dissolution of these materials induced by the radiolysis of water. Results indicate an inhibiting effect of the CO x water on the oxidative dissolution. In the presence of iron, two different behaviors are observed. Under alpha irradiation as the one expected in the geological disposal, the alteration of UO 2 matrix and MO x fuel is very strongly inhibited because of the consumption of radiolytic oxidative species by iron in solution leading to the precipitation of Fe(III)-hydroxides on the pellets surface. On the contrary, under a strong beta/gamma irradiation field, alteration tracers indicate that the oxidative dissolution goes on and that uranium concentration in solution is controlled by the solubility of UO 2 (am,hyd). This is explained by the shifting of the redox front from the fuel surface to the bulk solution not protecting the fuel anymore. The developed geochemical (CHESS) and reactive transport (HYTEC) models correctly represent the main results and occurring mechanisms. (author) [fr

  14. Disposal of high level and long lived radioactive waste in deep geological formation

    International Nuclear Information System (INIS)

    Niezborala, J.M.; Hoorelbeke, J.M.

    2000-01-01

    The status of ANDRA's research program on high level and long lived waste corresponds to the start of construction of the Meuse/Haute-Marne Underground Research Laboratory in an argillite layer, as well as to the selection in 1999 of preliminary disposal concepts corresponding to this layer. The paper describes the preliminary concepts dealing with transuranic waste, high level vitrified waste and potentially disposed spent fuel. Provision is made for a high level of flexibility, in particular with regard to options of reversibility of the disposal process, and to potential evolutions of the waste inventory. These concepts were selected for research purpose to assess by the year 2006 the feasibility of a potential repository, with.respect in particular to safety rules. The paper mentions the research targets of the program aiming at answering major scientific and technological questions raised by the concepts. The program includes the fitting and validation of the modelling, on the basis in particular of the experimental work to be carried out in the Underground Research Laboratory, making it possible to dimension the disposal concepts and to assess their safety. (authors)

  15. Safety and performance assessment of geologic disposal systems for nuclear wastes

    International Nuclear Information System (INIS)

    Peltonen, E.

    1987-01-01

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

  16. Measurement and modeling of flow through unsaturated heterogeneous rock in the context of geologic disposal of nuclear waste

    International Nuclear Information System (INIS)

    Sagar, B.; Bagtzoglou, A.C.; Green, R.T.; Stothoff, S.A.

    1995-01-01

    Deep geologic disposal of high-level and transuranic waste is currently being pursued vigorously. Assessing long-term performance of such repositories involves laboratory and field measurements, and numerical modeling. There exist two primary characteristics, associated with assessing repository performance, that define problems of modeling and measurement of non-isothermal flow through geologic media exposed to variable boundary conditions (e.g., climatic changes). These are: (1) the large time scale (tens of thousands of years) and highly variable space scale (from one meter to 10 5 meters); and (2) the hierarchy of heterogeneities and discontinuities characterizing the medium. This paper provides an overview of recent work, conducted at the Center for Nuclear Waste Regulatory Analyses (CNWRA), related to laboratory experiments, consideration of similitude, and numerical modeling of flow through heterogeneous media under non-homogeneous boundary conditions. As discussed, there exist neither good methods of measuring flows at these scales nor are there adequate similitude analyses that would allow reasonable scaling up of laboratory-scale experiments. Reliable assessment of long-term geologic repositories will require sophisticated geostatistical models capable of addressing variables scales of heterogeneities conditioned with observed results from adequately sized field-scale experiments conducted for sufficiently long durations

  17. Use of comparative assessment framework for comparison of geological nuclear waste and CO2 disposal technologies

    Energy Technology Data Exchange (ETDEWEB)

    Streimikiene, Dalia

    2010-09-15

    Comparative assessment of few future energy and climate change mitigation options for Lithuania in 2020 performed indicated that nuclear and combined cycle gas turbine technologies are very similar energy options in terms of costs taking into account GHG emission reduction costs. Comparative assessment of these energy options requires evaluation of the potentials and costs for geological CO2 and nuclear waste storage as the main uncertainties in comparative assessment of electricity generation technologies are related with these back-end technologies. The paper analyses the main characteristics of possible geological storage of CO2 and NW options in Lithuania.

  18. 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)

  19. 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)

  20. Measurement method of the distribution coefficient on the sorption process. Basic procedure of the method relevant to the barrier materials used for the deep geological disposal: 2006

    International Nuclear Information System (INIS)

    2006-08-01

    This standard was approved by Atomic Energy Society of Japan after deliberation of the Subcommittee on the Radioactive Waste Management, the Nuclear Cycle Technical Committee and the Standard Committee, and after obtaining about 600 comments from specialists of about 30 persons. This document defines the basic measurement procedure of the distribution coefficient (hereafter referred as Kd) to judge the reliability, reproducibility and applications and to provide the requirements for inter-comparison of Kd for a variety of barrier materials used for deep geological disposal of radioactive wastes. The basic measurement procedure of Kd is standardized, following the preceded standard, 'Measurement Method of the Distribution Coefficient on the Sorption Process - Basic Procedure of Batch Method Relevant to the Barrier Materials Used for the Shallow Land Disposal: 2002 (hereafter referred as Standard for the Shallow Land Disposal)', and considering recent progress after its publication and specific issues to the deep geological disposal. (J.P.N.)

  1. Preliminary paper - Integrated control process for the development of the mined geologic disposal system

    International Nuclear Information System (INIS)

    Daniel, Russell B.; Harbert, Kevin R.; Calloway, David E.

    1997-01-01

    The US Department of Energy (DOE) Order 430.1, Life Cycle Asset Management, begins to focus DOE Programs and Projects on the total system life cycle instead of looking at project execution or operation as individual components. As DOE begins to implement this order, the DOE Management and Operating contractors must develop a process to control not only the contract baseline but also the overall life cycle baseline. This paper presents an integrated process that is currently being developed on the Yucca Mountain Project for DOE. The process integrates the current contract/project baseline management process with the management control process for design and the configuration management change control process

  2. 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.)

  3. Albedo Neutron Dosimetry in a Deep Geological Disposal Repository for High-Level Nuclear Waste.

    Science.gov (United States)

    Pang, Bo; Becker, Frank

    2017-04-28

    Albedo neutron dosemeter is the German official personal neutron dosemeter in mixed radiation fields where neutrons contribute to personal dose. In deep geological repositories for high-level nuclear waste, where neutrons can dominate the radiation field, it is of interest to investigate the performance of albedo neutron dosemeter in such facilities. In this study, the deep geological repository is represented by a shielding cask loaded with spent nuclear fuel placed inside a rock salt emplacement drift. Due to the backscattering of neutrons in the drift, issues concerning calibration of the dosemeter arise. Field-specific calibration of the albedo neutron dosemeter was hence performed with Monte Carlo simulations. In order to assess the applicability of the albedo neutron dosemeter in a deep geological repository over a long time scale, spent nuclear fuel with different ages of 50, 100 and 500 years were investigated. It was found out, that the neutron radiation field in a deep geological repository can be assigned to the application area 'N1' of the albedo neutron dosemeter, which is typical in reactors and accelerators with heavy shielding. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  4. China's deep geological disposal program for high level radioactive waste, background and status 1998

    International Nuclear Information System (INIS)

    Ju Wang; Xu Guoqing; Guo Yonghai

    2001-01-01

    This paper presents the background and progress made in the study of China's high level radioactive waste, including site screening, site evaluation, the study on radionuclide migration, bentonite, natural analogue studies, and performance assessment, etc. The study on Beishan area, the potential area for China's geological repository, is also presented in this paper. (author)

  5. Modelling the long-term evolution of geological radwaste disposal facilities

    International Nuclear Information System (INIS)

    Dames and Moore International Twickenham

    1990-01-01

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

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

    International Nuclear Information System (INIS)

    1982-01-01

    For the final disposal of conditioned radioactive wastes clay formations have plasticity, low permeability and high sorption capacity in their favour. Their disadvantage lies in their thermal conductivity and moisture content. The aim of this document is to take stock of the state of the art pertaining to the thermal phenomena linked to the dispoasl of conditioned radioactive wastes. The study, limited to normal, non-accident operating conditions, considers vitrified wastes cast in metal containers and disposal of in an underground infrastructure built in clay. The composition and characteristics of clays can vary widely between formations and even between sites, since the nature and content of argillaceous and other minerals depend on age, sedimentation conditions, depth, origin of the sediments, etc. This study is therefore limited to a specific clay in a specific deposit, i.e., the Boom clay located at Mol beneath the CEN/SCK establishment

  7. Geologic waste disposal and a model for the surface movement of radionuclides

    International Nuclear Information System (INIS)

    Helton, J.; Iman, R.; Brown, J.; Schreurs, S.

    1979-01-01

    A model for the surface movement of radionuclides is presented. This model, which is referred to as the Pathways Model, was constructed in a NRC project to develop a methodology to assess the risk associated with the goelogic disposal of high-level radioactive waste. The methodology development involves work in two major areas: (a) models for physical processes, and (b) statistical techniques for the use and assessment of these models. The presentation of the Pathways Model involves topics from both areas

  8. Site characterization field manual for near surface geologic disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    McCray, J.G.; Nowatzki, E.A.

    1985-01-01

    This field manual has been developed to aid states and regions to do a detailed characterization of a proposed near-surface low-level waste disposal site. The field manual is directed at planners, staff personnel and experts in one discipline to acquaint them with the requirements of other disciplines involved in site characterization. While it can provide a good review, it is not designed to tell experts how to do their job within their own discipline

  9. Process and research method of radionuclide migration in high level radioactive waste geological disposal system

    International Nuclear Information System (INIS)

    Chen Rui; Zhang Zhanshi

    2014-01-01

    Radionuclides released from waste can migrate from the repository to the rock and soil outside. On the other hand, nuclides also are retarded by the backfill material. Radionuclide migration is the main geochemical process of the waste disposal. This paper introduces various methods for radionuclide migration research, and give a brief analysis of the geochemical process of radionuclide migration. Finally, two of the most important processes of the radionuclide migration have been instanced. (authors)

  10. Aspects of governance in the practical implementation of the concept of reversibility for deep geological disposal. Report no. 308

    International Nuclear Information System (INIS)

    Reaud, C.; Schieber, C.; Schneider, T.; Gadbois, S.; Heriard Dubreuil, G.

    2010-01-01

    The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia). In France, the issue of reversibility for a deep geological disposal was introduced in the Act of December 30, 1991 on the possible options to manage radioactive waste. The Act of June 28, 2006 relative to sustainable management of materials and radioactive waste confirmed the option, by calling for a reversible waste disposal facility in a deep geologi