所属领域：
钍基熔盐堆核能系统
资源类型：
数理科学和化学
/ 物理学
/ 原子核物理学、高能物理学
/ 原子核物理学
文献作者：
OHSAWA, T; INOUE, M
文献发表年份：
1994
文献期刊：
ANNALS OF NUCLEAR ENERGY
文献摘要：The yields and energy spectra of primary neutrons emitted from spent molten-salt fuel have been analyzed as a function of cooling time. It was found that (alpha, n) reactions made a major contribution to neutron production in the Th-based molten-salt fuel, in contrast to the case of U-fuels for LWRs where spontaneous fission was a main contributor. One of the consequences of this was that the neutron yield continued to increase to reach a maximum 8-9 yr after irradiation, reflecting variation of the concentrations of strong alpha-emitters in the Th series. This peculiar characteristic requires that attention should be paid to neutron- as well as gamma-shielding of storage facilities of spent molten-salt fuel.
文献类型： Article
文献语种： English
文献作者地址： KYUSHU UNIV,DEPT NUCL ENGN,FUKUOKA 812,JAPAN