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Nuclear Waste Discussion Draft - FLO13341 - 113th Congress - 1st Session
Nuclear Waste Discussion Draft - FLO13341 - 113th Congress - 1st Session
To establish a new organization to manage nuclear waste, provide a consensual process for siting nuclear waste facilities, ensure adequate funding for managing nuclear waste, and for other purposes.
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together Synthesis of the FSC National Workshop and Community Visit Bar-le-Duc, France
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together Synthesis of the FSC National Workshop and Community Visit Bar-le-Duc, France
The 7th Forum on Stakeholder Confidence (FSC) National Workshop and Community Visit was held on 7-9 April 2009 in Bar-le-Duc, France. It was organized with teh assistance of the CLIS (the Local Information and Oversight Committee) and the financial and logistical support of Andra, France's National Agency for the Management of Radioactive Waste.
Interim Storage of Spent Nuclear Fuel A Safe, Flexible, and Cost-Effective Near-Term Approach to Spent Fuel Management
Interim Storage of Spent Nuclear Fuel A Safe, Flexible, and Cost-Effective Near-Term Approach to Spent Fuel Management
The management of spent fuel from nuclear power
plants has become a major policy issue for virtually every
nuclear power program in the world. For the nuclear industry, finding sufficient capacity for storage and processing or
disposal of spent fuel is essential if nuclear power plants are
to be allowed to continue to operate. At the same time, the
options chosen for spent fuel management can have a substantial impact on the political controversies, proliferation
risks, environmental hazards, and economic costs of the
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.
Summary of the Nuclear Waste Administration Act of 2013 Discussion Draft
Summary of the Nuclear Waste Administration Act of 2013 Discussion Draft
The Nuclear Waste Administration Act of 2013 discussion draft is intended to implement the recommendations of the Blue Ribbon Commission on America’s Nuclear Future to establish a nuclear waste administration and create a consent-based process for siting nuclear waste facilities. The bill enables the federal government to fulfill its commitment to managing nuclear waste, ending the costly liability the government bears for its failure to dispose of commercial spent fuel.
Nuclear Waste Bill to Implement the Blue Ribbon Commission's Recommendations Section-by-Section Summary of Discussion Draft - April 2013
Nuclear Waste Bill to Implement the Blue Ribbon Commission's Recommendations Section-by-Section Summary of Discussion Draft - April 2013
In General: The Nuclear Waste Administration Act of 2013 includes most of the language of S.3469, the Nuclear Waste Administration Act of 2012. The most significant change in the 2013 bill is the provision linking construction and siting of a consolidated storage facility to progress on a repository. The 2012 Act prohibited storage of any spent nuclear fuel beyond 10,000 metric tons until the Administration concluded a repository consent agreement.
Nuclear Waste Bill Feedback
Nuclear Waste Bill Feedback
On April 25, 2013, Senators Wyden, Alexander, Feinstein, and Murkowski released a draft bill to create a sustainable, participatory process for managing nuclear waste. The senators requested comments and suggestions on the draft bill, as well as on the alternative language for siting an interim storage facility proposed by Senators Alexander and Feinstein. In addition, the senators posed eight questions on which they sought comments.
Closing Yucca Mountain: Litigation Associated with Attempts to Abandon the Planned Nuclear Waste Repository
Closing Yucca Mountain: Litigation Associated with Attempts to Abandon the Planned Nuclear Waste Repository
Passed in 1982, the Nuclear Waste Policy Act (NWPA) was an effort to establish an explicit statutory basis for the Department of Energy (DOE) to dispose of the nation’s most highly radioactive nuclear waste. The NWPA requires DOE to remove spent nuclear fuel from commercial nuclear power plants, in exchange for a fee, and transport it to a permanent geologic repository or an interim storage facility before permanent disposal. Defense-related high-level<br>waste is to go into the same repository.
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.