Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor
文献类型:期刊论文
作者 | Jamil, Zeeshan1,2; Zou, Jun1; Hao, Lijuan1; Hu, Liqin1,2 |
刊名 | ANNALS OF NUCLEAR ENERGY |
出版日期 | 2018-12-01 |
卷号 | 122期号:无页码:155-162 |
ISSN号 | 0306-4549 |
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 |
英文摘要 | 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. |
WOS关键词 | VALIDATION ; SUPERMC ; SYSTEM ; CODE |
资助项目 | 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 |
语种 | 英语 |
出版者 | PERGAMON-ELSEVIER SCIENCE LTD |
WOS记录号 | WOS:000447107700015 |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/39723] |
专题 | 合肥物质科学研究院_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 |
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. |
入库方式: OAI收割
来源:合肥物质科学研究院
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