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OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

Author(s)
Nouri, A.
Publication Date
The OECD/NEA “Burn-up Credit Criticality Benchmark” working group has studied the effect of axial burn-up profile on the criticality of a realistic PWR spent fuel transport cask (Phase II-B). The final results of this benchmark are presented and analysed in this report. Nine basic cases and two additional accident configurations were considered with the following varying parameters: burn-up (0 GWd/t for fresh fuel, 30 and 50 GWd/t), fuel composition (actinides only and actinides with fifteen fission products), axial burn-up discretisation (1 or 9 zones).
criticality pwr fuel transport cask end effect source convergence burnup axial burnup profile

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

Author(s)
DOE
Publication Date

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.

criticality spent fuel fission products cross-section data safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle benchmarks used fuel

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

Author(s)
Office of Civilian Radioactive Waste Management
Publication Date

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.

criticality spent fuel fission products cross-section data benchmark safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle used fuel

EPRI Review of Geologic Disposal for Used Fuel and High-Level Radioactive Waste: Volume III --Review of National Repository Programs

EPRI Review of Geologic Disposal for Used Fuel and High-Level Radioactive Waste: Volume III --Review of National Repository Programs

Author(s)
Electric Power Research Institute
Publication Date

The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has left the U.S. program for management of used fuel and high level radioactive waste (HLW)
in a state of uncertainty. In concert with this major policy reset and in response to the resulting
policy vacuum, the President directed the Energy Secretary to establish the Blue Ribbon
Commission on America’s Nuclear Future (BRC) “…to conduct a comprehensive review of
policies for managing the back end of the nuclear fuel cycle and to provide recommendations for

disposal yucca mountain repository deep geological disposal international hlw repository programs waste management used fuel spent nuclear fuel high level radioactive waste (hlw) hlw repository

Letter from the BRC to the Members of the South Carolina Congressional Delegation

Letter from the BRC to the Members of the South Carolina Congressional Delegation

Author(s)
Blue Ribbon Commission
Publication Date

Dear Members of the South Carolina Congressional Delegation:
Thank you all for your letter of October 27th. We appreciate hearing your views on the
Yucca Mountain project, the safety benefits of deep geologic disposal, and the
importance of the retaining the H Canyon facility at the Department of Energy’s
Savannah River Site.
In our draft report, the Commission finds that deep geologic disposal is an essential
component of a comprehensive nuclear waste management system. Your comments

deep geological disposal blue ribbon commission savannah river site

Standards & Regulations for the Geologic Disposal of Spent Nuclear Fuel and High-Level Waste

Standards & Regulations for the Geologic Disposal of Spent Nuclear Fuel and High-Level Waste

Author(s)
Rodney C. Ewing
Publication Date

This paper draws on my experience as a reviewer of the scientific programs and performance assessments of the geological repository for transuranic waste at the Waste Isolation Pilot Plant in New Mexico and the proposed repository for spent nuclear fuel and high-level waste at Yucca Mountain in Nevada. In addition, I have served on numerous committees of the National Research Council that have addressed many aspects of nuclear waste management.

disposal high level waste spent fuel yucca mountain repository deep geological disposal wipp blue ribbon commission used fuel

Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test

SED Publication Type

Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test

Author
Atkin, S. D.
Publication Date

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.

spent fuel fission gas turkey point burnup used fuel

SCOPING STUDY OF SALT DOMES, BASALTS AND CRYSTALLINE ROCK AS RELATED TO LONG TERM RISK MODELING FOR DEEP GEOLOGIC DISPOSAL OF NUCLEAR WASTE

SED Publication Type

SCOPING STUDY OF SALT DOMES, BASALTS AND CRYSTALLINE ROCK AS RELATED TO LONG TERM RISK MODELING FOR DEEP GEOLOGIC DISPOSAL OF NUCLEAR WASTE

Author
Golder Associates, CONSULTING MINING AND GEOTECHNICAL ENGINEERS
Publication Date

The purpose of this study is to provide a preliminary geotechnical data base sufficient to initiate the development of Long-Term Risk Models (LTRM), for salt domes, basalt and crystalline rock, and identify technical issues requiring additional investigation.

deep geological disposal siting geo-technical salt domes basalt crystalline rock risk models

Radioactive Waste Management Programmes in OECD/NEA Member Countries: Sweden

SED Publication Type

Radioactive Waste Management Programmes in OECD/NEA Member Countries: Sweden

Author
Organization for Economic Cooperation and Development/Nuclear Energy Agency
Publication Date

Summary of radioactive waste and management programs in Sweden, including national nuclear energy context; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; authorities and implementing organizations; financing; and public information.

disposal deep geological disposal financing civilian radioactive waste management program research and development

Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Results and Perspectives

SED Publication Type

Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Results and Perspectives

Author
ANDRA
Publication Date

A report documenting ANDRA's research on deep disposal of radioactive waste, examining both clay and granite formations.

deep geological disposal research and development
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