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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.
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues - Results from Phase 1 on UOx Fuels
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues - Results from Phase 1 on UOx Fuels
Although there are many reactor system benchmarks in the literature, they mostly
concentrate on the reactor system in isolation with only a few considering the fuel cycle.
However, there is currently increased emphasis on the performance of reactor systems
linked to their associated fuel cycle (Generation-IV for example). The published
international benchmark studies which relate to burn-up depletion calculations are
restricted to specific aspects of the fuel cycle:
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.
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.
Fuel Cycle Potential Waste Inventory for Disposition
Fuel Cycle Potential Waste Inventory for Disposition
The purpose of this report is to provide an estimate of potential waste inventory and waste form
characteristics for the DOE UNF and HLW and a variety of commercial fuel cycle alternatives in order to
support subsequent system-level evaluations of disposal system performance. This report is envisioned as
a “living document” which will be revised as specific alternative fuel cycles are developed
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
The Future of Nuclear Power: An Interdisciplinary MIT Study (2003)
The Future of Nuclear Power: An Interdisciplinary MIT Study (2003)
"This study analyzes what would be required to retain nuclear power as a significant option for reducing greenhouse gas emissions and meeting growing needs for electricity supply. Our analysis is guided by a global growth scenario that would expand current worldwide nuclear generating capacity almost threefold, to 1000 billion watts, by the year 2050. Such a deployment would avoid 1.8 billion tonnes of carbon emissions annually from coal plants, about 25% of the increment in carbon emissions otherwise expected in a business-as-usual scenario.
The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study
The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study
"In 2003 MIT published the interdisciplinary study The Future of Nuclear Power. The underlying motivation was that nuclear energy, which today provides about 70% of the “zero”-carbon electricity in the U.S., is an important option for the market place in a low-carbon world. Since that report, major changes in the U.S. and the world have taken place as described in our 2009 Update of the 2003 Future of Nuclear Power Report. Concerns about climate change have risen: many countries have adopted restrictions on greenhouse gas emissions to the atmosphere, and the U.S.
Nuclear Power Joint Fact-Finding
Nuclear Power Joint Fact-Finding
"Nuclear power has long been controversial; consequently, the debate about its reemergence requires a fresh assessment of the facts about the technology, its economics and regulatory oversight, and the risks and benefits of its expansion. In the past year, the Keystone Center assembled a group of 27 individuals (see the Endorsement page for a list of Participants) with extensive experience and unique perspectives to develop a joint understanding of the “facts” and for an objective interpretation of the most credible information in areas where uncertainty persists.
The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study, Summary Report
The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study, Summary Report
<strong>This is a summary report. The full report is <a href="https://curie.ornl.gov/content/future-nuclear-fuel-cycle-interdisciplin…;
A review of the Nuclear Waste Disposal Problem
A review of the Nuclear Waste Disposal Problem
Dealing with the problems posed by nuclear waste management is a major issue confronting continued use of the nuclear fuel cycle. Large amounts of radioactive wastes have already been generated as a result of past nuclear reactor operations, but these wastes are being temporarily kept in aboveground storage facilities awaiting a government policy decision on final disposition. Although research on various technologies to dispose of radioactive wastes is given high priority, a commercial waste disposal facility is not expected to be in operation before 1985.
Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test
Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test
The destructive examination results of five light water reactor rods from the Turkey Point Unit 3 reactor are presented. The examinations included fission gas collection and analyses, burnup and hydrogen analyses, and a metallographic evaluation of the fuel, cladding, oxide, and hydrides. The rods exhibited a low fission gas release with all other results appearing representative for pressurized water reactor fuel rods with similar burnups (28 GWd/MTU) and operating histories.
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.
Global Nuclear Energy Partnership
Global Nuclear Energy Partnership
GNEP Presentation to 2008 ECA Annual Conference
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
Closing the US Fuel Cycle: Siting Considerations for the Global Nuclear Energy Partnership Facilities-Siting the Advanced Fuel Cycle Facility
Closing the US Fuel Cycle: Siting Considerations for the Global Nuclear Energy Partnership Facilities-Siting the Advanced Fuel Cycle Facility
The Global Nuclear Energy Partnership (GNEP), launched in February, 2006, proposes to introduce used nuclear fuel recycling in the United States (U.S.) with improved proliferation-resistance and a more effective waste management approach. This program is evaluating ways to close the fuel cycle in a manner that introduces the most advanced technologies of today and builds on recent breakthroughs in U.S. national laboratories while drawing on international and industry partnerships.
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.
IAEA Information Circular - Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
IAEA Information Circular - Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
1. The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the International Atomic Energy Agency at its headquarters from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the International Atomic Energy Agency and will remain open for signature until its entry into force. 2.
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.