- 著者
- Takahisa YAMAMOTO Koshi MITACHI Takashi SUZUKI
- 出版者
- 社団法人 日本機械学会
- 雑誌
- JSME International Journal Series B Fluids and Thermal Engineering (ISSN:13408054)
- 巻号頁・発行日
- vol.48, no.3, pp.610-617, 2005 (Released:2006-02-15)
- 参考文献数
- 13
- 被引用文献数
- 16 24
The Molten Salt Reactor (MSR) is a thermal neutron reactor with graphite moderation and operates on the thorium-uranium fuel cycle. The feature of the MSR is that fuel salt flows inside the reactor during the nuclear fission reaction. In the previous study, the authors developed numerical model with which to simulate the effects of fuel salt flow on the reactor characteristics. In this study, we apply the model to the steady-state analysis of a small MSR system and estimate the effects of fuel flow. The model consists of two-group neutron diffusion equations for fast and thermal neutron fluxes, transport equations for six-group delayed neutron precursors and energy conservation equations for fuel salt and the graphite moderator. The following results are obtained: (1) in the rated operation condition, the peaks of the neutron fluxes slightly move toward the bottom from the center of the reactor and the delayed neutron precursors are significantly carried by the fuel salt flow, and (2) the extension of residence time in the external-loop system and the rise of the fuel inflow temperature show weak negative reactivity effects, which decrease the neutron multiplication factor of the small MSR system.