Published 2022 | Version v1
Book

Development of cross-section data set repository and interpolation code system, LOCUS

  • 1. Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

Description

The cross-section data library and its interpolation code, LOCUS, is being developed for the acceleration of cross-section data generation for use in ANC9 core calculations. The initial version of LOCUS targets a range of applicability for widely used Westinghouse PWR fuel types using standard UO2 fuel and its associated burnable poison types (i.e. Integral Fuel Burnable Absorber (IFBA), Wet Annular Burnable Absorber (WABA), and any combination thereof). The interpolation parameters are U235 fuel enrichment, fuel pellet theoretical density and IFBA thickness. These parameters are individually investigated to determine their interdependence and to evaluate the order and increment size for each parameter. The linear interpolation in pellet density and the quadratic interpolation in enrichment and IFBA thickness showed good agreements as compared to the reference solutions. These three parameters are interpolated at the same time by tri-linear/quadratic Lagrange interpolation to generate a cross-section data set at target enrichment, pellet density and IFBA thickness. ANC9 calculation results by the LOCUS interpolated cross-section data set are compared with that by the reference cross-section set. They agreed very well in k-infinity, pin power, control rod worth, etc. The cross-section data sets generated by LOCUS are also applied to Reload Safety Analysis Checklist (RSAC) calculations in full-core geometry and compared with reference solutions obtained by non-interpolated cross-section data sets. All calculation errors are very small and negligible. These results demonstrate that LOCUS can supply the cross-section data sets consistent with the current non-interpolated cross-section data sets. (authors)

Availability note (English)

Available (CD Rom) from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)
Part of:
Proceedings of the international conference on physics of reactors - Physor 2022

Additional details

Publishing Information

Publisher
ANS - American Nuclear Society
Imprint Place
La Grange Park (United States)
ISBN
978-0-89448-787-3
Imprint Title
Proceedings of the international conference on physics of reactors - PHYSOR 2022
Imprint Pagination
3701 p.
Journal Page Range
p. 2618-2626

Conference

Title
International conference on physics of reactors
Acronym
PHYSOR 2022
Dates
15-20 May 2022
Place
Pittsburg (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
54042121
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CROSS SECTIONS; INTERPOLATION; L CODES; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS
Descriptors DEC
COMPUTER CODES; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT

Optional Information

Notes
2 refs.