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Probabilistic External Criticality Evaluation (SCPB: N/A)
Probabilistic External Criticality Evaluation (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide a probabilistic evaluation of the potential for criticality of fissile material which has been transported from a geologic repository containing breached waste packages of commercial spent nuclear fuel (SNF). This analysis is part of a continuing investigation of the probability of criticality resulting from the emplacement of spent nuclear fuel in a geologic repository.
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Preliminary Transportation, Aging and Disposal Canister System Performance Specification Requirements Rationale, Revision B
Preliminary Transportation, Aging and Disposal Canister System Performance Specification Requirements Rationale, Revision B
The purpose of this document is to provide the requirements rationale for the current version of the Preliminary Transportation, Aging and Disposal Canister System Performance Specification; WMO-TADCS-000001.
Geochemistry Model Validation Report: External Accumulation Model
Geochemistry Model Validation Report: External Accumulation Model
The purpose of this report is to document and validate the external accumulation model that predicts accumulation of fissile materials in the invert, fractures and lithophysae in the rock beneath a degrading waste package containing spent nuclear fuel (SNF) in the monitored geologic repository at Yucca Mountain. (Lithophysae are hollow, bubblelike structures in the rock composed of concentric shells of finely crystalline alkali feldspar, quartz, and other materials (Bates and Jackson 1984 [DIRS 128109], p.
EQ6 Calculations for Chemical Degradation of Pu-Ceramic Waste Packages
EQ6 Calculations for Chemical Degradation of Pu-Ceramic Waste Packages
In this study, the long-term geochemical behavior of waste package (WP), containing Pu-ceramic, was modeled. The ceramic under consideration contains Ti, U, Pu, Gd and Hf in a pyrochlore structure; the Gd and Hf stabilize the mineral structure, but are also intended to provide criticality control. The specific study objectives were to determine:
1) the extent to which criticality control material, suggested for this WP design, will remain in the WP after corrosion/dissolution of the initial package configuration (such that it can be effective in preventing criticality), and
Analysis of Critical Benchmark Experiments for Configurations External to WP
Analysis of Critical Benchmark Experiments for Configurations External to WP
The Disposal Criticality Analysis Methodology Topical Report (Reference 1) states that the accuracy of the criticality analysis methodology (MCNP Monte Carlo code and cross-section data) designated to assess the potential for criticality of various configurations in the Yucca Mountain proposed repository is established by evaluating appropriately selected benchmark critical experiments.
Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste Package (SCPB: N/A)
Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste Package (SCPB: N/A)
This study is prepared by the Mined Geologic Disposal System (MODS) Waste Package Development Department (WPDD) to provide input to a separate evaluation on the probablility of criticality in the far- field environment. These calculations are performed in sufficient detail to provide conservatively bounding configurations to support separate probabilistic analyses.
Report On External Criticality of Plutonium Waste Forms In A Geologic Repository
Report On External Criticality of Plutonium Waste Forms In A Geologic Repository
This report presents the analyses and results for the potential occurrence of external criticality events which could result from plutonium waste forms emplaced in a geologic repository similar to the one being developed at Yucca Mountain. The analyses evaluate both the MOX spent fuel and the immobilized plutonium waste forms in a repository if the waste package has degraded and if the fissile material has migrated to the invert and out into the far-field.
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Making Nuclear Waste Governable: Deep Underground Disposal and the Challenge of Reversibility
Making Nuclear Waste Governable: Deep Underground Disposal and the Challenge of Reversibility
This book is the result of a collaboration that began over two years ago between researchers from the social sciences and Andra engineers and natural scientists. Contributions to the various chapters have been discussed and enhanced, especially during the workshop and the interdisciplinary conference both held by Andra in 2008 and 2009<br>respectively.
Emergence of Collective Action and Environmental Networking in Relation to Radioactive Waste Management
Emergence of Collective Action and Environmental Networking in Relation to Radioactive Waste Management
This paper explores the relationship between the national environmental movement and nuclear technology in relation to a local emergent group. The historical development of nuclear technology in this country has followed a path leading to continued fear and mistrust of waste management by a portion of the population. At the forefront of opposition to nuclear technology are people and groups endorsing environmental values.
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
This work was performed to suggest possible strategies for geoscientific classifications in the siting process of a high-level repository. To develop a feasible method for geoscientific classifications, a number of factors of a philosophical character, related to the purpose of the classifications, need to be accounted for. Many different approaches can be visualized, and this report was not intended to present a complete classification methodology.
Geological Disposal of Higher Activity Radioactive Wastes
Geological Disposal of Higher Activity Radioactive Wastes
This is one of three CoRWM reports to Government in 2009. The reports are about: <br><br>_ interim storage of higher activity wastes (including waste conditioning, packaging and transport, and the management of materials that may be declared to be wastes) <br>_ the implementation of geological disposal of higher activity wastes (this report) <br>_ research and development for interim storage and geological disposal. <br><br>The reports cover the three strands of the Government_s Managing Radioactive Waste Safely programme.
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
The Committee on Radioactive Waste Management was asked by Government in 2003 to make recommendations for the long-term management of the UK’s higher activity wastes that would both protect the public and the environment, and inspire public confidence. To do this, we have combined a technical assessment of options with ethical considerations, examination of overseas experience and a wide-ranging programme of engagement both with the public and with interested parties (stakeholders). I am happy to present our recommendations in the pages that follow.
Committee on Radioactive Waste Management Seventh Annual Report
Committee on Radioactive Waste Management Seventh Annual Report
This is the seventh CoRWM Annual Report. It summarises the outcomes of CoRWM’s scrutiny and advice work during the year. It also contains the Committee’s views on the current status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK. All the Committee Members have contributed to this Report and I am grateful to Marion Hill and the Secretariat for all their hard work in compiling it.
Committee on Radioactive Waste Management Eighth Annual Report
Committee on Radioactive Waste Management Eighth Annual Report
This is the eighth CoRWM Annual Report. It summarises CoRWM’s scrutiny and advice for the financial year ending on 31 March 2012. It also contains the Committee’s views on the status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK at June 2012.
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
The Committee on Radioactive Waste Management (CoRWM) has carried out an assessment of the generic Disposal System Safety Case (gDSSC) published by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) in February 2011. The assessment covered the whole suite of gDSSC documents, and related RWMD reports on research and development (R&D) and site characterisation.
Everything You Ever Wanted to Know about Radioactive Waste Management
Everything You Ever Wanted to Know about Radioactive Waste Management
Explanation of Radioactivity and Radioactive waste
Additional Media Studies for Site Suitability Criteria
Additional Media Studies for Site Suitability Criteria
Site suitability studies at LLL to date have considered repositories in bedded salt and shale.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
. On 25 March 1999 the Government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has already drawn the second National Report for the purposes of Review Meetings of the Contracting Parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report
The United States of America ratified the “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management” (Joint Convention) on April 9, 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their nuclear activities into compliance with general safety standards and practices. This first Review Meeting of the Contracting Parties under the Joint Convention is scheduled to take place in November 2003 in Vienna, Austria.