Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Xiao-Bin Xia"'
Publikováno v:
Nuclear Science and Techniques. 33
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9b5d9fca482d51d033be061183031b9e
https://doi.org/10.1007/s41365-022-01032-y
https://doi.org/10.1007/s41365-022-01032-y
Publikováno v:
Vacuum. 203:111288
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f054394a7d285ae538be50a170c12f9c
https://doi.org/10.1016/j.vacuum.2022.111288
https://doi.org/10.1016/j.vacuum.2022.111288
Autor:
Jun Cai, Xiao-Bin Xia, Zhi-Hong Zhang, Jianhua Wang, Zhi-Cheng Qian, Chang-Yuan Li, Guo-Qing Zhang
Publikováno v:
Nuclear Science and Techniques. 32
A liquid fueled thorium molten salt reactor (TMSR-LF), one of the Generation IV reactors, was designed by the Shanghai Institute of Applied Physics, Chinese Academy of Sciences. This study uses the`rt code to calculate the neutron and gamma dose rate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::66ee573d80c9b7e17818376c0e1b711b
https://doi.org/10.1007/s41365-021-00857-3
https://doi.org/10.1007/s41365-021-00857-3
Autor:
Xiao-Bin Xia, Kai Wang, He Liubin, Hong Zhang, Peng Honghua, Liu Xueyang, Zhenghua Qian, Yanbo Qiao, Qin Qiang, Wang Shuai, Jun Cai, Yulan Li
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 317:947-957
In order to reduce the deposition of inorganic salt in continuous reactor during the treatment of radioactive spent extraction solvent by supercritical water oxidation, the solubilities of five kinds of radioactive inorganic salts were investigated a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5872b86a599ad9325d6eeaf9d94906e
https://doi.org/10.1007/s10967-018-5939-5
https://doi.org/10.1007/s10967-018-5939-5
Autor:
He Liubin, Zhenghua Qian, Qin Qiang, Yanbo Qiao, Xiao-Bin Xia, Wang Hongyu, Zheng Li, Liu Xueyang, Ma Hongjun, Chen Kun, Wang Shuai
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 314:1169-1176
Radioactive spent extraction solvent was treated by supercritical water oxidation. In this work, influences of reaction conditions on total organic carbon (TOC) removal, the volume percentage of CO2 yielded, and the distributions of radionuclides in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5fedfdbcda1d0be7f473911c40f44d0d
https://doi.org/10.1007/s10967-017-5445-1
https://doi.org/10.1007/s10967-017-5445-1
Publikováno v:
Nuclear Science and Techniques. 30
The thorium molten salt reactor–liquid fuel (TMSR-LF1) has inherent safety features. The accident occurrence possibility and their consequences are much lower for the TMSR-LF1 than that of traditional reactors. Based on accident analysis, the maxim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30f11838422cc7c8056da60bea000cc1
https://doi.org/10.1007/s41365-019-0605-3
https://doi.org/10.1007/s41365-019-0605-3
Publikováno v:
Science China Materials. 59:279-286
Radioactive alkali fluoride salts are generated during the operation of molten salt reactors (MSRs) and reprocessing of their spent fuel, and appear in the form of fluidity granule, or powder. In order to prevent the radionuclides from being released
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f91933b52d95448e7a24454bed68eb97
https://doi.org/10.1007/s40843-016-5010-x
https://doi.org/10.1007/s40843-016-5010-x
Publikováno v:
Nuclear Science and Techniques. 29
Molecular dynamics (MD) simulations were conducted to investigate the structural and chemical environment of aluminum in aluminophosphate glasses. Such glasses have the potential for application in the disposal of radioactive fluoride waste from molt
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6599168cfe9593e2c4d4e5b702692132
https://doi.org/10.1007/s41365-018-0443-8
https://doi.org/10.1007/s41365-018-0443-8
Publikováno v:
Nuclear Science and Techniques. 27
Tritium release is one of the most concerning topics in nuclear power plants. Here, the tritium production in a 2 MW liquid-fueled molten salt experimental reactor (TMSR-LF1) was calculated by ORIGEN-S with an updated cross-section library generated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ee50722a60142b2028ec0953866b8f7c
https://doi.org/10.1007/s41365-016-0100-z
https://doi.org/10.1007/s41365-016-0100-z
Publikováno v:
Nuclear Science and Techniques. 27
Radioactive fluoride wastes are generated during the operation of molten salt reactors (MSRs) and reprocessing of their spent fuel. Immobilization of these wastes in borosilicate glass is not feasible because of the very low solubility of fluorides i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::522c8d5f0ff9b1d4936a25fc4cfc00b5
https://doi.org/10.1007/s41365-016-0059-9
https://doi.org/10.1007/s41365-016-0059-9