A validated methodology for evaluating burnup credit in spent fuel casks
- 1. Oak Ridge National Lab., TN (USA)
- 2. Sandia National Labs., Albuquerque, NM (USA)
Description
The concept of allowing reactivity credit for the transmuted state of spent fuel offers both economic and risk incentives. This paper presents a general overview of the technical work being performed in support of the US Department of Energy (DOE) program to resolve issues related to the implementation of burnup credit. An analysis methodology is presented along with information representing the validation of the method against available experimental data. The experimental data that are applicable to burnup credit include chemical assay data for the validation of the isotopic prediction models, fresh fuel critical experiments for the validation of criticality calculations for various cask geometries, and reactor restart critical data to validate criticality calculations with spent fuel. The methodology has been specifically developed to be simple and generally applicable, therefore giving rise to uncertainties or sensitivities which are identified and quantified in terms of a percent bias in keff. Implementation issues affecting licensing requirements and operational procedures are discussed briefly. 24 refs., 3 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91015612; NTIS; INIS; US Govt. Printing Office Dep.Files
23001769.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- CONF-910993--7
Conference
- Title
- International conference on nuclear criticality (ICNC) safety.
- Dates
- 9-13 Sep 1991.
- Place
- Oxford (United Kingdom).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23001769
- Subject category
- S42: ENGINEERING; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CASKS; COMPUTER CODES; CRITICALITY; EVALUATION; REACTIVITY; SPENT FUEL STORAGE; SPENT FUELS; STATISTICAL MODELS; WASTE TRANSPORTATION
- Descriptors DEC
- CONTAINERS; ENERGY SOURCES; FUELS; MANAGEMENT; MATERIALS; MATHEMATICAL MODELS; NUCLEAR FUELS; REACTOR MATERIALS; STORAGE; WASTE MANAGEMENT
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400; AC04-76DP00789
- Funding organization
- USDOE, Washington, DC (United States).