Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / prepared by D.E. Mueller [and three others].

Format:

Book

Government document

Author/Creator:

Mueller, D. E., author.

Contributor:

U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards, issuing body.

Oak Ridge National Laboratory, issuing body.

Language:

English

Subjects (All):

Fission products--Handling.

Fission products.

Monte Carlo method.

Actinide elements.

Fuel burnup (Nuclear engineering).

Spent reactor fuels--Storage.

Spent reactor fuels.

Spent reactor fuels--Transportation.

Pressurized water reactors.

Physical Description:

1 online resource ([73] pages) : color illustrations

Place of Publication:

Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, September 2015.

Summary:

The U.S. Nuclear Regulatory Commission (NRC) Division of Spent Fuel Storage and Transportation recently issued Interim Staff Guidance (ISG) 8, Revision 3. This ISG provides guidance for burnup credit (BUC) analyses supporting transport and storage of PWR pressurized water reactor (PWR) fuel in casks. Revision 3 includes guidance for addressing validation of criticality (keff) calculations crediting the presence of a limited set of fission products and minor actinides (FP & MA). Based on previous work documented in NUREG/CR-7109, recommendation 4 of ISG-8, Rev. 3, includes a recommendation to use 1.5 or 3% of the FP & MA worth to conservatively cover the bias due to the specified FP & MAs. This bias is supplementary to the bias and bias uncertainty resulting from validation of keff calculations for the major actinides in SNF and does not address extension to actinides and fission products beyond those identified herein. The work described in this report involves comparison of FP & MA worths calculated using SCALE and MCNP with ENDF/B-V, -VI, and -VII based nuclear data and supports use of the 1.5% FP & MA worth bias when either SCALE or MCNP codes are used for criticality calculations, provided the other conditions of the recommendation 4 are met. The method used in this report may also be applied to demonstrate the applicability of the 1.5% FP & MA worth bias to other codes using ENDF/B V, VI or VII based nuclear data. The method involves use of the applicant s computational method to generate FP & MA worths for a reference SNF cask model using specified spent fuel compositions. The applicant s FP & MA worths are then compared to reference values provided in this report. The applicants FP & MA worths should not exceed the reference results by more than 1.5% of the reference FP & MA worths.

Notes:

"Manuscript completed: May 2014; Date published: September 2015."

Title from title screen (viewed on Sept. 18, 2015).

"NUREG/CR-7205."

"ORNL/TM-2012/544."

Includes bibliographical references (page 21).

Other Format:

Print version: Mueller, D.E. Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks

OCLC:

921844183