Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Xuzhong Kang"'
Publikováno v:
Journal of Nuclear Engineering, Vol 5, Iss 2, Pp 168-185 (2024)
The lifespan of core graphite under neutron irradiation in a commercial molten salt reactor (MSR) has an important influence on its economy. Flattening the fast neutron flux (≥0.05 MeV) distribution in the core is the main method to extend the grap
Externí odkaz:
https://doaj.org/article/e133f703f47e441ea052906177f183ae
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 1, Pp 213-227 (2023)
The SM-MSR (small modular molten salt reactor) has a good prospect for development with regards to combining the superiority of the molten salt reactor and modularization technologies, showing the advantages of safety, reliability, low economic cost
Externí odkaz:
https://doaj.org/article/8f670cb03ed6474faabd8331532ae2ef
Publikováno v:
Volume 4: SMRs, Advanced Reactors, and Fusion.
In a molten salt reactor, the volume change in the primary loop may lead to an overflow of fuel salt, which will challenge the radioactive containment. Several factors, such as the thermal expansion, graphite dimensional change caused by fast neutron
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f52ff7d6c87fbccc48687fdb627232cf
https://doi.org/10.1115/icone29-90295
https://doi.org/10.1115/icone29-90295
Publikováno v:
International Journal of Energy Research. 45:11976-11991
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f34d7ecfcaeb8e22cd819da36293b492
https://doi.org/10.1002/er.5964
https://doi.org/10.1002/er.5964
Publikováno v:
Annals of Nuclear Energy. 133:707-717
Critical Experiment Device (cold) was established for research on the physics characteristics of Molten Salt Reactor (MSR) in 1970s, at Shanghai Institute of Applied Physics, China. Neutron flux distribution was measured for different core structures
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::01d2ae0ac3611d4d4eb3688744b3d432
https://doi.org/10.1016/j.anucene.2019.07.018
https://doi.org/10.1016/j.anucene.2019.07.018
Publikováno v:
Annals of Nuclear Energy. 132:391-403
The Heavy Water moderated Molten Salt Reactor (HW-MSR) is a novel concept of a thermal heterogeneous nuclear reactor and pursues for Thorium-Uranium (Th-U) breeding. It adopts heavy water rather than graphite as moderator while employs the same liqui
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a243415f277aba694499d669af2c8b42
https://doi.org/10.1016/j.anucene.2019.04.043
https://doi.org/10.1016/j.anucene.2019.04.043
Autor:
Ye Dai, Xuzhong Kang, Chunyan Zou, Wei Guo, Menglu Tan, Rui Yan, Jingen Chen, Guifeng Zhu, Yang Zou
Publikováno v:
International Journal of Energy Research. 43:5775-5787
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fbb55f5935d3a264b053f755746defd4
https://doi.org/10.1002/er.4676
https://doi.org/10.1002/er.4676
Autor:
Ming Dai, Guimin Liu, Xiao-Han Yu, Xiangzhou Cai, Guifeng Zhu, Yu Shihe, Yang Zou, Xuzhong Kang, Rui Yan
Publikováno v:
Progress in Nuclear Energy. 110:24-29
A multi-group cross section method was developed based on MOBAT code to save computing time. First, three PWR pin cell benchmark cases were computed by MOBAT, MCODE and SCALE. The results of the separate benchmark cases are consistent with each other
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb9c1d72ee4be1f5b99634b3e9ce1322
https://doi.org/10.1016/j.pnucene.2018.09.003
https://doi.org/10.1016/j.pnucene.2018.09.003
Publikováno v:
Nuclear Science and Techniques. 32
The production of radionuclides 90Sr and 131I in molten salt reactors is an attractive option to address the global shortage of radionuclides. This study evaluated the production characteristics of 90Sr and 131I in a modular molten salt reactor, such
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bf5a076e9ab237147e4d056e8873a0fe
https://doi.org/10.1007/s41365-021-00867-1
https://doi.org/10.1007/s41365-021-00867-1