Published 1991 | Version v1
Report Open

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.

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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).