Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor

Kang Seog Kim; Byoung-Kyu Jeon; Andrew Ward; Ugur Mertyurek; Matthew Jessee; William Wieselquist

doi:10.3390/jne5030017

Journal of Nuclear Engineering (Jul 2024)

Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor

Kang Seog Kim,
Byoung-Kyu Jeon,
Andrew Ward,
Ugur Mertyurek,
Matthew Jessee,
William Wieselquist

Affiliations

Kang Seog Kim: Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, One Bethel Valley Road, P.O. Box 2008, MS-6172, Oak Ridge, TN 37831, USA
Byoung-Kyu Jeon: Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, One Bethel Valley Road, P.O. Box 2008, MS-6172, Oak Ridge, TN 37831, USA
Andrew Ward: Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USA
Ugur Mertyurek: Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, One Bethel Valley Road, P.O. Box 2008, MS-6172, Oak Ridge, TN 37831, USA
Matthew Jessee: Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, One Bethel Valley Road, P.O. Box 2008, MS-6172, Oak Ridge, TN 37831, USA
William Wieselquist: Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, One Bethel Valley Road, P.O. Box 2008, MS-6172, Oak Ridge, TN 37831, USA

DOI: https://doi.org/10.3390/jne5030017
Journal volume & issue: Vol. 5, no. 3
pp. 246 – 259

Abstract

Read online

This study was conducted to validate the SCALE/Polaris v6.3.0–PARCS v3.4.2 code procedure with the Evaluated Nuclear Data File (ENDF)/B-VII.1 AMPX 56-group library for pressurized water reactor (PWR) analysis, by comparing simulated results with measured data for critical experiments and operating PWRs. Uncertainties of the SCALE/Polaris–PARCS code procedure for PWR analysis were evaluated in the validation for the PWR key nuclear parameters such as critical boron concentrations, reactivity, control bank work, temperature coefficients, and pin and assembly power peaking factors.

Published in Journal of Nuclear Engineering

ISSN: 2673-4362 (Online)
Publisher: MDPI AG
Country of publisher: Switzerland
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: https://www.mdpi.com/journal/jne

About the journal

Abstract

Keywords