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FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
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.
Legal Analysis of Commission Recommendations for Near-Term Actions
Legal Analysis of Commission Recommendations for Near-Term Actions
At the request of the staff to the Blue Ribbon Commission on America’s Nuclear Future (“BRC”), we have reviewed whether certain recommendations in the BRC’s July 29, 2011 Draft Report respecting near-term actions by the Department of Energy (“DOE”) or other officers or agencies in the Executive Branch can be implemented under existing law. These recommendations relate to:
(1) Initial steps to site, license and construct consolidated interim storage facilities for spent nuclear fuel (“spent fuel”);
Legal Background and Questions Concerning the Federal Government’s Contractual Obligations Under the “Standard Contracts” with “Utilities”
Legal Background and Questions Concerning the Federal Government’s Contractual Obligations Under the “Standard Contracts” with “Utilities”
This Memorandum analyzes issues related to the Standard Contract between the U.S. Department of Energy (“DOE”) and the “utilities.” Beginning with a discussion of specific provisions of the Standard Contract, this Memorandum then analyzes the status of lawsuits involving the Standard Contract, reviews issues related to on-site storage of spent fuel and HLW, and assesses the prospects for modifying the current waste-disposal regime through Federal legislation or amendments to the Standard Contract.
Attachment 1 - Memo, Reply to Letter to Mr. Tim Frazier
Attachment 1 - Memo, Reply to Letter to Mr. Tim Frazier
This memo sets forth the Office of Standard Contract Management's current estimate of the US Government's liability in connection with the Government's partial breach of the "standard contracts" that it executed pursuant to the NWPA of 1982. The Office of Standard Contract Management estimates that liability, as of today and based on the analysis and qualifications set forth below, to be $15.4 billion.
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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.