Institutional Repository of Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Hefei, Anhui 230031, China
Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor | |
Jamil, Zeeshan1,2; Zou, Jun1![]() | |
2018-12-01 | |
发表期刊 | ANNALS OF NUCLEAR ENERGY
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ISSN | 0306-4549 |
摘要 | Advanced computation to deal with sophisticated nuclear systems and their process mainly relies on competent nuclear data libraries. The library could significantly alter the simulation results. In this study, the competence of a Hybrid Evaluated Nuclear Data Library, called HENDL, has been strengthened by employing it in performing calculations for integral neutron physics parameters. For this purpose, SuperMC code was used to model and simulate an SFR (Sodium-cooled fast reactor), BFS-62-3A - the critical experiment performed at BFS2 facility in Russia. The critical assembly in its full heterogeneous configuration containing four fuel-zones was modeled. The calculations were performed to estimate the criticality, reactivity effects, spectral indices and fission rates in radial direction. The sensitivity study was also carried out to see the influence of any change by the experimental uncertainties in the material data described in the critical experiment. The accuracy and trustworthiness being the vital properties that any neutron data library should possess were thus testified and proved thereafter for the aforementioned fast spectrum advanced reactor. The results so obtained were in good agreement with the experiment and the study hence enabled the HENDL library to be validated/benchmarked. (C) 2018 Elsevier Ltd. All rights reserved. |
关键词 | Validation/Benchmarking HENDL BFS-62-3A SuperMC Heterogeneous Criticality Reactivity effects Spectral indices Fission rates Sensitivity study |
DOI | 10.1016/j.anucene.2018.08.040 |
关键词[WOS] | VALIDATION ; SUPERMC ; SYSTEM ; CODE |
收录类别 | SCI |
语种 | 英语 |
资助项目 | National Natural Science Foundation of China[11605233] ; Industrialization Fund ; National Magnetic Confinement Fusion Science Program of China[2014GB112001] ; National Magnetic Confinement Fusion Science Program of China[2014GB112001] ; Industrialization Fund ; National Natural Science Foundation of China[11605233] |
WOS研究方向 | Nuclear Science & Technology |
WOS类目 | Nuclear Science & Technology |
WOS记录号 | WOS:000447107700015 |
出版者 | PERGAMON-ELSEVIER SCIENCE LTD |
引用统计 | |
文献类型 | 期刊论文 |
条目标识符 | http://ir.hfcas.ac.cn:8080/handle/334002/39723 |
专题 | 中国科学院核能安全技术研究所 |
通讯作者 | Jamil, Zeeshan |
作者单位 | 1.Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China 2.Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China |
第一作者单位 | 中国科学院核能安全技术研究所 |
通讯作者单位 | 中国科学院核能安全技术研究所 |
推荐引用方式 GB/T 7714 | Jamil, Zeeshan,Zou, Jun,Hao, Lijuan,et al. Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor[J]. ANNALS OF NUCLEAR ENERGY,2018,122(无):155-162. |
APA | Jamil, Zeeshan,Zou, Jun,Hao, Lijuan,&Hu, Liqin.(2018).Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor.ANNALS OF NUCLEAR ENERGY,122(无),155-162. |
MLA | Jamil, Zeeshan,et al."Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor".ANNALS OF NUCLEAR ENERGY 122.无(2018):155-162. |
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