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Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft
Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of Department of Energy (DOE) standardized Spent Nuclear Fuel (SNF) canisters.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.
Storage of Spent Nuclear Fuel (Specific Safety Guide)
Storage of Spent Nuclear Fuel (Specific Safety Guide)
This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup.
Radionuclide Screening
Radionuclide Screening
The waste forms under consideration for disposal in the repository at Yucca Mountain contain scores of radionuclides. It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from a nuclear waste repository at Yucca Mountain.
Preclosure Consequence Analyses
Preclosure Consequence Analyses
The purpose of this calculation is to demonstrate that the preclosure performance objectives specified in 10 CFR 63.111(a) and 10 CFR 63.111(b) (Reference 2.2.1) have been met for the proposed design and operations in the geologic repository operations area (GROA) during normal operations and Category 1 event sequences, and following Category 2 event sequences. Category 1 event sequences are those natural and human-induced event sequences that are expected to occur one or more times before permanent closure of the repository.
Canister Handling Facility Criticality Safety Calculations
Canister Handling Facility Criticality Safety Calculations
This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.
Stakeholder Involvement in Decision Making: A Short Guide to Issues, Approaches and Resources
Stakeholder Involvement in Decision Making: A Short Guide to Issues, Approaches and Resources
Radioactive waste management is embedded in broader societal issues such as the
environment, risk management, energy, health policy and sustainability. In all
these fields, there is an increasing demand for public involvement, participation
and engagement. Involvement may take different forms at different phases and
can include sharing information, consulting, dialoguing or deliberating on
decisions with relevant stakeholders. Stakeholder involvement should be seen as a
WP 2 Appendix 10 Balance of Power: Principles and Good Practices for Local Stakeholders to Influence National Decision-making Processes
WP 2 Appendix 10 Balance of Power: Principles and Good Practices for Local Stakeholders to Influence National Decision-making Processes
Our basic position is that the outcomes of policy-making in radioactive waste management (RWM) should be driven by the will of the people through democratic processes. Achieving this inclusiveness requires good practices to increase local influence on what is essentially a national policy process. However inclusiveness poses significant practical problems; can society afford lengthy and costly consultation processes, often perceived as inefficient and ineffective?
Stakeholder Involvement and Confidence in the Process of Decision-making for the Disposal of Spent Nuclear Fuel in Finland
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
We, the Environmental Protection Agency (EPA), are promulgating public health and safety standards for radioactive material stored or disposed of in the potential repository at Yucca Mountain, Nevada. Section 801 of the Energy Policy Act of 1992 (EnPA, Pub. L. 102Ð486) directs us to develop these standards. Section 801 of the EnPA also requires us to contract with the National Academy of Sciences (NAS) to conduct a study to provide findings and recommendations on reasonable standards for protection of the public health and safety.
CORWM’S ADVICE TO GOVERNMENT ON OPTIONS FOR THE ACCELERATION OF THE IMPLEMENTATION OF GEOLOGICAL DISPOSAL
CORWM’S ADVICE TO GOVERNMENT ON OPTIONS FOR THE ACCELERATION OF THE IMPLEMENTATION OF GEOLOGICAL DISPOSAL
This paper is a response to a request from the Department of Energy and Climate Change (DECC) for CoRWM’s advice on the 2011 review of options for accelerating the geological disposal programme carried out by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA).
WP 3 Quality of decision-making process Proposed Framework for Decision-making Processes
WP 3 Quality of decision-making process Proposed Framework for Decision-making Processes
The long-term governance of radioactive waste is complex socio-technical issue. The disposition of radioactive waste is decided on ethical grounds, having to take into account a variety of other dimensions (society, economy, ecology, politics, time, space, and technology). Thereto, a study of variants is required. Decision theory, in principle, takes diverse options as a starting point begin as the basis of a decision.
WP 2 Appendix 8 Mechanisms for Local Influence on National Decision Making Processes in Radioactive Waste Management
WP 2 Appendix 8 Mechanisms for Local Influence on National Decision Making Processes in Radioactive Waste Management
This document develops further the questions offered to stakeholders in the Berlin Meeting (see Appendix). It describes mechanisms that local stakeholders can use to influence national decision-making processes in radioactive waste management.
WP 2 Appendix 9 Principles and Good Practices for Local Actors to Influence National Decision-Making Processes
WP 2 Appendix 9 Principles and Good Practices for Local Actors to Influence National Decision-Making Processes
The outcomes of policy-making in radioactive waste management (RWM) should be driven by the will of the people through democratic processes. Achieving this inclusiveness requires good practices to increase local influence on what is essentially a national policy process. However inclusiveness poses significant practical problems; can society afford lengthy and costly consultation processes, often perceived as inefficient and ineffective?
Final Report: Influence of Local Actors on National Decision-making Processes WP2
Final Report: Influence of Local Actors on National Decision-making Processes WP2
Work Package 2 (WP2) focused on the ways in which local stakeholders can influence national decision-making processes on radioactive waste management (RWM). The participants in WP2 were particularly interested in examining how local stakeholders could contribute to national debates. Their interest stemmed from the fact that participants from France, Spain and the United Kingdom — who made up the majority of the WP2 group — were engaged, as stakeholders, in the decision-making processes that were under way in each of those countries.
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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Finland signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The major generators of radioactive waste in Finland are the two nuclear power plants, the Loviisa and Olkiluoto plants. The Loviisa plant has two PWR units, operated by Fortum Power and Heat Oy, and the Olkiluoto plant two BWR units, operated by Teollisuuden Voima Oy.