Neutronic design and evaluation of the solid microencapsulated fuel in LWR
Solid Microencapsulated Fuel (SMF) is a type of solid fuel rod design that disperses TRISO coated fuel particles directly into a kind of matrix. SMF is expected to provide improved performance because of the elimination of cladding tube and associated failure mechanisms. This study focused on the ne...
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| Format: | Article |
| Language: | English |
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Elsevier
2022-08-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573322001401 |
| _version_ | 1811344098345353216 |
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| author | Qianliang Deng Songyang Li Dingqu Wang Zhihong Liu Fei Xie Jing Zhao Jingang Liang Yueyuan Jiang |
| author_facet | Qianliang Deng Songyang Li Dingqu Wang Zhihong Liu Fei Xie Jing Zhao Jingang Liang Yueyuan Jiang |
| author_sort | Qianliang Deng |
| collection | DOAJ |
| description | Solid Microencapsulated Fuel (SMF) is a type of solid fuel rod design that disperses TRISO coated fuel particles directly into a kind of matrix. SMF is expected to provide improved performance because of the elimination of cladding tube and associated failure mechanisms. This study focused on the neutronics and some of the fuel cycle characteristics of SMF by using OpenMC. Two kinds of SMFs have been designed and evaluated - fuel particles dispersed into a silicon carbide matrix and fuel particles dispersed into a zirconium matrix. A 7x7 fuel assembly with increased rod diameter transformed from the standard NHR200-II 9x9 array was also introduced to increase the heavy metal inventory. A preliminary study of two kinds of burnable poisons (Erbia & Gadolinia) in two forms (BISO and QUADRISO particles) was also included. This study found that SMF requires about 12% enriched UN TRISO particles to match the cycle length of standard fuel when loaded in NHR200-II, which is about 7% for SMF with increased rod diameter. Feedback coefficients are less negative through the life of SMF than the reference. And it is estimated that the average center temperature of fuel kernel at fuel rod centerline is about 60 K below that of reference in this paper. |
| first_indexed | 2024-04-13T19:41:44Z |
| format | Article |
| id | doaj.art-028a5dcb47764e9a9eebd6cebe6c5c5a |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-04-13T19:41:44Z |
| publishDate | 2022-08-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-028a5dcb47764e9a9eebd6cebe6c5c5a2022-12-22T02:32:52ZengElsevierNuclear Engineering and Technology1738-57332022-08-0154830953105Neutronic design and evaluation of the solid microencapsulated fuel in LWRQianliang Deng0Songyang Li1Dingqu Wang2Zhihong Liu3Fei Xie4Jing Zhao5Jingang Liang6Yueyuan Jiang7Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China; Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China; Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China; Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China; Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China; Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China; Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing, China; Corresponding author. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China.Solid Microencapsulated Fuel (SMF) is a type of solid fuel rod design that disperses TRISO coated fuel particles directly into a kind of matrix. SMF is expected to provide improved performance because of the elimination of cladding tube and associated failure mechanisms. This study focused on the neutronics and some of the fuel cycle characteristics of SMF by using OpenMC. Two kinds of SMFs have been designed and evaluated - fuel particles dispersed into a silicon carbide matrix and fuel particles dispersed into a zirconium matrix. A 7x7 fuel assembly with increased rod diameter transformed from the standard NHR200-II 9x9 array was also introduced to increase the heavy metal inventory. A preliminary study of two kinds of burnable poisons (Erbia & Gadolinia) in two forms (BISO and QUADRISO particles) was also included. This study found that SMF requires about 12% enriched UN TRISO particles to match the cycle length of standard fuel when loaded in NHR200-II, which is about 7% for SMF with increased rod diameter. Feedback coefficients are less negative through the life of SMF than the reference. And it is estimated that the average center temperature of fuel kernel at fuel rod centerline is about 60 K below that of reference in this paper.http://www.sciencedirect.com/science/article/pii/S1738573322001401Neutronics designAccident tolerant fuelDepletion analysisBurnable poison |
| spellingShingle | Qianliang Deng Songyang Li Dingqu Wang Zhihong Liu Fei Xie Jing Zhao Jingang Liang Yueyuan Jiang Neutronic design and evaluation of the solid microencapsulated fuel in LWR Nuclear Engineering and Technology Neutronics design Accident tolerant fuel Depletion analysis Burnable poison |
| title | Neutronic design and evaluation of the solid microencapsulated fuel in LWR |
| title_full | Neutronic design and evaluation of the solid microencapsulated fuel in LWR |
| title_fullStr | Neutronic design and evaluation of the solid microencapsulated fuel in LWR |
| title_full_unstemmed | Neutronic design and evaluation of the solid microencapsulated fuel in LWR |
| title_short | Neutronic design and evaluation of the solid microencapsulated fuel in LWR |
| title_sort | neutronic design and evaluation of the solid microencapsulated fuel in lwr |
| topic | Neutronics design Accident tolerant fuel Depletion analysis Burnable poison |
| url | http://www.sciencedirect.com/science/article/pii/S1738573322001401 |
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