Validation of Code Packages for Light Water Reactor Physics Analysis

A special issue of Journal of Nuclear Engineering (ISSN 2673-4362).

Deadline for manuscript submissions: 31 May 2025 | Viewed by 2211

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Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37830, USA
Interests: computational reactor physics; nuclear data; transport and diffusion theory; resonance self-shielding methods; modeling and simulation; in-core fuel management; multiphysics simulation
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Dear Colleagues,

Light water reactor (LWR) analysis can be performed using a typical 2-step code package, which includes a 2D lattice physics code and a 3D nodal diffusion code with thermal–hydraulic feedback capabilities. The 2D lattice physics code processes few-group assembly-homogenized cross sections, incorporating the functionalization of various reactor states. The 3D nodal code conducts 3D whole-core calculations for LWR multi-physics analysis, including neutronics, thermal-hydraulics and transmutation. In recent years, direct 3D whole-core multi-physics analysis has become more practical, providing more reliable simulation results and thus enhancing LWR technology.

Nuclear vendors validate their code packges by estimating the uncertainties in key nuclear parameters via comparisons between the simulated and measured data, which can be used in in-core fuel management. In recent years, various LWR-based small modular reactors (SMRs) have been developed. Evaluating the uncertainties of the design code packages for these SMRs is challenging due to the lack of available measured data, which may require different approacges to uncertainty analysis to be employed, for example, by integrating individual components of uncertainty, such as those arising from nuclear data and manufacturing.

This Special Issue of JNE will focus on the validation of 2-step and direct LWR analysis code packages by comparing simulation results with plant-measured data, and by performing uncertainty analysis based on nuclear data and manufacturing uncertainties. The scope of this Special Issue includes validations of the analysis code packages used for the key nuclear parameters of operating LWRs, LWR-based SMR, and advanced LWRs.

Dr. Kang Seog Kim
Guest Editor

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Keywords

  • light water reactor
  • validation
  • uncertainty
  • reactor physics

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Published Papers (2 papers)

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Research

14 pages, 4475 KiB  
Article
Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor
by Kang Seog Kim, Andrew Ward, Ugur Mertyurek, Mehdi Asgari and William Wieselquist
J. Nucl. Eng. 2024, 5(3), 260-273; https://doi.org/10.3390/jne5030018 - 1 Aug 2024
Viewed by 1077
Abstract
The SCALE/Polaris–PARCS code procedure has been used in the confirmatory analysis for boiling water reactors by the US Nuclear Regulatory Commission. In this study, 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 was validated by [...] Read more.
The SCALE/Polaris–PARCS code procedure has been used in the confirmatory analysis for boiling water reactors by the US Nuclear Regulatory Commission. In this study, 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 was validated by comparing the simulated results with the measured data for operating boiling water reactors, including Peach Bottom Unit 2 cycles 1–3, Hatch Unit 1 cycles 1–3, and Quad Cities Unit 1 cycles 1–3. The uncertainties and biases of the SCALE/Polaris–PARCS code package for boiling water reactor physics analysis were evaluated in the validation for key nuclear parameters such as reactivity and traversing in-core probe data. Full article
(This article belongs to the Special Issue Validation of Code Packages for Light Water Reactor Physics Analysis)
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14 pages, 5726 KiB  
Article
Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor
by Kang Seog Kim, Byoung-Kyu Jeon, Andrew Ward, Ugur Mertyurek, Matthew Jessee and William Wieselquist
J. Nucl. Eng. 2024, 5(3), 246-259; https://doi.org/10.3390/jne5030017 - 23 Jul 2024
Viewed by 778
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 [...] Read more.
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. Full article
(This article belongs to the Special Issue Validation of Code Packages for Light Water Reactor Physics Analysis)
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