Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor-Reference-Cited by-同舟云学术

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

Published:2024-07-23 Issue:3 Volume:5 Page:246-259
ISSN:2673-4362
Container-title:Journal of Nuclear Engineering
language:en
Short-container-title:JNE

Author:

Kim Kang¹,Jeon Byoung-Kyu¹,Ward Andrew²,Mertyurek Ugur¹^ORCID,Jessee Matthew¹,Wieselquist William¹

Affiliation:

1. 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

2. Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USA

Abstract

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.

Funder

US Nuclear Regulatory Commission Office

Publisher

MDPI AG

Link

https://www.mdpi.com/2673-4362/5/3/17/pdf

Reference24 articles.

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