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Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
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 First 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 First 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 First National Report
Nuclear Waste Policy Act (Section 112) - Environmental Assessment, Overview, Davis Canyon Site, Utah
Nuclear Waste Policy Act (Section 112) - Environmental Assessment, Overview, Davis Canyon Site, Utah
In February 1983, the U.S. Department of Energy (DOE) identified the Davis Canyon site in Utah as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories.
Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository under the Nuclear Waste Policy Act of 1982
Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository under the Nuclear Waste Policy Act of 1982
For more than half a century, since nuclear science helped us win World War II and ring in the Atomic Age, scientists have known that the Nation would need a secure, permanent facility in which to dispose of radioactive wastes. Twenty years ago, when Congress adopted the Nuclear Waste Policy Act of 1982 (NWPA or "the Act"), it recognized the overwhelming consensus in the scientific community that the best option for such a facility would be a deep underground repository.
Nuclear Waste Policy Act (Section 112) - Environmental Assessment, Yucca Mountain Site, Nevada Research and Development Area, Nevada, Volume 1
Nuclear Waste Policy Act (Section 112) - Environmental Assessment, Yucca Mountain Site, Nevada Research and Development Area, Nevada, Volume 1
By the end of this century, the United States plans to begin operating the first geologic repository for the permanent disposal of commercial spent nuclear fuel and high-level radioactive Waste. Public Law 97-425, the Nuclear waste Policy Act of 1982 (the Act), specifies the process for selecting a repository site, and constructing, operating, closing, and decommissioning the repository.
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canadian National Report -- Final Report
This report demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. A collaboration by government, industry and the regulatory body, this document focuses specifically on the progress of long-term management initiatives for spent fuel and radioactive waste in Canada, revisions and updates to Canada’s Third National Report and comments and issues raised at the Third Review Meeting.
The U.S. Environmental Protection Agency’s Public Health and Safety Standards for Yucca Mountain, Nevada (40 CFR Part 197) - 9072
The U.S. Environmental Protection Agency’s Public Health and Safety Standards for Yucca Mountain, Nevada (40 CFR Part 197) - 9072
In 2001, as directed by the Energy Policy Act of 1992, the U.S. Environmental Protection Agency (EPA) issued public health and environmental radiation protection standards for the proposed repository at Yucca Mountain, Nevada. Several parties sued the Agency on a myriad of aspects of the rule. The Court ruled in EPA’s favor in all aspects of the case but one, and returned the standards to the Agency in 2004. In 2005, EPA proposed amendments to the standards. Following public hearings and a public review period, the final amendments were issued in September 2008.
Appendix C - Report of the Blue Ribbon Commission on America's Nuclear Future - Report to the Secretary of Energy
Appendix C - Report of the Blue Ribbon Commission on America's Nuclear Future - Report to the Secretary of Energy
The Blue Ribbon Commission on America_s Nuclear Future (BRC) was formed by the Secretary<br>of Energy at the request of the President to conduct a comprehensive review of policies for<br>managing the back end of the nuclear fuel cycle and recommend a new strate
OECD/NEA: United States
OECD/NEA: United States
Response to "Multiattribute Utility Analysis of Sites Nominated for Characterization for the First Radioactive-Waste Repository"
Response to "Multiattribute Utility Analysis of Sites Nominated for Characterization for the First Radioactive-Waste Repository"
Identifying remaining socio-technical challenges at the national level: France
Identifying remaining socio-technical challenges at the national level: France
France isn’t only a country known for its cheese… it’s also a country of nuclear power. With its 58 nuclear reactors (63,000 megawatts), producing 79% of the country’s electricity, France is arguably the world’s leader in the production of nuclear energy. It is estimated that the relative contribution of nuclear energy to power production in France will decline to 70% in 2020 - the main reason for this being governmental investments into renewable energies.
Belgian Workshop (November 2003) - Executive Summary and International Perspective
Belgian Workshop (November 2003) - Executive Summary and International Perspective
History of Repository Regulations
History of Repository Regulations
Quality of Decision-making Processes: Decision-making processes in Radioactive Waste Governance - Insights and Recommendations WP3
Quality of Decision-making Processes: Decision-making processes in Radioactive Waste Governance - Insights and Recommendations WP3
Work Package 3 (WP 3) set out to provide practical recommendations for the design and implementation of a “robust” decision-making process (DMP) in radioactive waste governance/governance of radioactive waste management (RWG).
Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance
Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.
Frequency of SNF Misload for Uncanistered Fuel Waste Package
Frequency of SNF Misload for Uncanistered Fuel Waste Package
The purpose of this engineering calculation is to estimate the frequency of misloading spent nuclear fuel (SNF) assemblies that would result in exceeding the criticality design basis of a waste package (WP). This type of misload - a reactivity misload - results from the incorrect placement of one or more fuel assemblies into a waste package such that the criticality controls do not match the required controls for the fuel assemblies. An actual criticality event can not occur in a WP unless a moderator (e.g. water) is present.
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
(AFR) criticality safety analyses be validated against experimental measurements. If credit for the
negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark
computational methods against spent fuel critical configurations. This report summarizes a portion
of the ongoing effort to benchmark AFR criticality analysis methods using selected critical
configurations from commercial pressurized-water reactors (PWR).
In-Drift Precipitates/Salts Model
In-Drift Precipitates/Salts Model
This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
Radioactive Waste Management and Decommissioning in Netherlands
Radioactive Waste Management and Decommissioning in Netherlands
Radioactive Waste Management and Decommissioning in Switzerland
Radioactive Waste Management and Decommissioning in Switzerland
Monitored Retrievable Storage Project Plan
Monitored Retrievable Storage Project Plan
The purpose of this document is to describe the Monitored Retrievable Storage (MRS) Project and to establish approved cost and schedule baselines against which overall progress and management effectiveness shall be measured. For the sake of brevity, this Project Plan will be referred to as the Plan throughout this document.