Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation

Among all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on neutron flux should be considered during the few-gro...

Full description

Bibliographic Details
Main Authors: Xianan Du, Xuewen Wu, Youqi Zheng, Yongping Wang
Format: Article
Language:English
Published: MDPI AG 2021-07-01
Series:Energies
Subjects:
Online Access:https://www.mdpi.com/1996-1073/14/13/4042
_version_ 1797528001128169472
author Xianan Du
Xuewen Wu
Youqi Zheng
Yongping Wang
author_facet Xianan Du
Xuewen Wu
Youqi Zheng
Yongping Wang
author_sort Xianan Du
collection DOAJ
description Among all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on neutron flux should be considered during the few-group cross-sections generation. Therefore, the purpose of this paper is to compare the influence whether the angular dependence on neutron flux is considered in the calculation of few-group cross sections for the reactivity effect calculation. In the study, the 1-D SN finite difference neutron transport equation solver was implemented in the TULIP of SARAX code system so that the high-order neutron flux could be obtained. Meanwhile, the improved Tone’s method was also applied. The numerical results were obtained based on three experimental FR cores, the JOYO MK-I core, ZPPR-9 core, and ZPPR-10B core. Both control rod worth and sodium void reactivity were calculated and compared with the measurement data. By summarizing and comparing the results of 46 cases, significant differences were found between different consideration of the neutronic analysis. The consideration of angular dependence on neutron flux distribution in the few-group cross-sections generation was beneficial to the neutronic design analysis of FR, especially for the reactivity effect calculation.
first_indexed 2024-03-10T09:51:53Z
format Article
id doaj.art-8ab20c0f6e2c47ebaca2479b984a217e
institution Directory Open Access Journal
issn 1996-1073
language English
last_indexed 2024-03-10T09:51:53Z
publishDate 2021-07-01
publisher MDPI AG
record_format Article
series Energies
spelling doaj.art-8ab20c0f6e2c47ebaca2479b984a217e2023-11-22T02:39:09ZengMDPI AGEnergies1996-10732021-07-011413404210.3390/en14134042Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections GenerationXianan Du0Xuewen Wu1Youqi Zheng2Yongping Wang3School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaSchool of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaSchool of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaSchool of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaAmong all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on neutron flux should be considered during the few-group cross-sections generation. Therefore, the purpose of this paper is to compare the influence whether the angular dependence on neutron flux is considered in the calculation of few-group cross sections for the reactivity effect calculation. In the study, the 1-D SN finite difference neutron transport equation solver was implemented in the TULIP of SARAX code system so that the high-order neutron flux could be obtained. Meanwhile, the improved Tone’s method was also applied. The numerical results were obtained based on three experimental FR cores, the JOYO MK-I core, ZPPR-9 core, and ZPPR-10B core. Both control rod worth and sodium void reactivity were calculated and compared with the measurement data. By summarizing and comparing the results of 46 cases, significant differences were found between different consideration of the neutronic analysis. The consideration of angular dependence on neutron flux distribution in the few-group cross-sections generation was beneficial to the neutronic design analysis of FR, especially for the reactivity effect calculation.https://www.mdpi.com/1996-1073/14/13/4042fast reactorreactivity effect calculationanisotropySARAX
spellingShingle Xianan Du
Xuewen Wu
Youqi Zheng
Yongping Wang
Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation
Energies
fast reactor
reactivity effect calculation
anisotropy
SARAX
title Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation
title_full Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation
title_fullStr Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation
title_full_unstemmed Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation
title_short Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation
title_sort reactivity effect evaluation of fast reactor based on angular dependent few group cross sections generation
topic fast reactor
reactivity effect calculation
anisotropy
SARAX
url https://www.mdpi.com/1996-1073/14/13/4042
work_keys_str_mv AT xianandu reactivityeffectevaluationoffastreactorbasedonangulardependentfewgroupcrosssectionsgeneration
AT xuewenwu reactivityeffectevaluationoffastreactorbasedonangulardependentfewgroupcrosssectionsgeneration
AT youqizheng reactivityeffectevaluationoffastreactorbasedonangulardependentfewgroupcrosssectionsgeneration
AT yongpingwang reactivityeffectevaluationoffastreactorbasedonangulardependentfewgroupcrosssectionsgeneration