Flux Density Distribution Measurement in Annular Fuel Reactor
The relative neutron flux density distribution is one of the essential physical parameters of the reactor. Measuring the relative neutron flux density distribution of the annular fuel zero-power reactor core has guiding significance for understanding the physical characteristics of the annular fuel...
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| Format: | Article |
| Language: | English |
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Editorial Board of Atomic Energy Science and Technology
2022-01-01
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| Series: | Yuanzineng kexue jishu |
| Subjects: | |
| Online Access: | https://www.aest.org.cn/CN/10.7538/yzk.2021.youxian.0254 |
| _version_ | 1811305111482269696 |
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| author | ZHANG Geng;LIU Feng;XIA Zhaodong;ZHU Qingfu;ZHANG Zhifeng |
| author_facet | ZHANG Geng;LIU Feng;XIA Zhaodong;ZHU Qingfu;ZHANG Zhifeng |
| author_sort | ZHANG Geng;LIU Feng;XIA Zhaodong;ZHU Qingfu;ZHANG Zhifeng |
| collection | DOAJ |
| description | The relative neutron flux density distribution is one of the essential physical parameters of the reactor. Measuring the relative neutron flux density distribution of the annular fuel zero-power reactor core has guiding significance for understanding the physical characteristics of the annular fuel core reactor and conducting safety analysis. In this paper, the γ activity of the gold foil at different positions on the outer surface of the fuel cell after irradiation was measured by foil activation method under polygonal loading of annular fuel core. The axial and radial relative neutron flux density distributions of fuel cell at different positions were obtained, and the measured values were compared with the values calculated by Monte Carlo theory. The results show that the maximum relative deviation between experimental measurement and theoretical calculation is within 12%. The measurement results of relative neutron flux density distribution are in line with the measure design expectations. The existing Monte Carlo analysis methods can better analyze the axial flux density distribution of the components in the reactor. This study provides essential data support for the engineering application of annular fuel. |
| first_indexed | 2024-04-13T08:19:36Z |
| format | Article |
| id | doaj.art-d4c1cf5ae6a041b0ad38a6c84fc083b5 |
| institution | Directory Open Access Journal |
| issn | 1000-6931 |
| language | English |
| last_indexed | 2024-04-13T08:19:36Z |
| publishDate | 2022-01-01 |
| publisher | Editorial Board of Atomic Energy Science and Technology |
| record_format | Article |
| series | Yuanzineng kexue jishu |
| spelling | doaj.art-d4c1cf5ae6a041b0ad38a6c84fc083b52022-12-22T02:54:41ZengEditorial Board of Atomic Energy Science and TechnologyYuanzineng kexue jishu1000-69312022-01-01561 121126Flux Density Distribution Measurement in Annular Fuel ReactorZHANG Geng;LIU Feng;XIA Zhaodong;ZHU Qingfu;ZHANG Zhifeng 0Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing 102413, ChinaThe relative neutron flux density distribution is one of the essential physical parameters of the reactor. Measuring the relative neutron flux density distribution of the annular fuel zero-power reactor core has guiding significance for understanding the physical characteristics of the annular fuel core reactor and conducting safety analysis. In this paper, the γ activity of the gold foil at different positions on the outer surface of the fuel cell after irradiation was measured by foil activation method under polygonal loading of annular fuel core. The axial and radial relative neutron flux density distributions of fuel cell at different positions were obtained, and the measured values were compared with the values calculated by Monte Carlo theory. The results show that the maximum relative deviation between experimental measurement and theoretical calculation is within 12%. The measurement results of relative neutron flux density distribution are in line with the measure design expectations. The existing Monte Carlo analysis methods can better analyze the axial flux density distribution of the components in the reactor. This study provides essential data support for the engineering application of annular fuel.https://www.aest.org.cn/CN/10.7538/yzk.2021.youxian.0254annular fuelneutron flux density distributionactivation method |
| spellingShingle | ZHANG Geng;LIU Feng;XIA Zhaodong;ZHU Qingfu;ZHANG Zhifeng Flux Density Distribution Measurement in Annular Fuel Reactor Yuanzineng kexue jishu annular fuel neutron flux density distribution activation method |
| title | Flux Density Distribution Measurement in Annular Fuel Reactor |
| title_full | Flux Density Distribution Measurement in Annular Fuel Reactor |
| title_fullStr | Flux Density Distribution Measurement in Annular Fuel Reactor |
| title_full_unstemmed | Flux Density Distribution Measurement in Annular Fuel Reactor |
| title_short | Flux Density Distribution Measurement in Annular Fuel Reactor |
| title_sort | flux density distribution measurement in annular fuel reactor |
| topic | annular fuel neutron flux density distribution activation method |
| url | https://www.aest.org.cn/CN/10.7538/yzk.2021.youxian.0254 |
| work_keys_str_mv | AT zhanggengliufengxiazhaodongzhuqingfuzhangzhifeng fluxdensitydistributionmeasurementinannularfuelreactor |