科研之友
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摘要
Seed and blanket (S&B) fuel blocks, which usually consist of a seed region with uranium in the center and a blanket region with thorium around the center, are a good way to utilize thorium. Thus it is interesting to introduce the conception of S&B fuel blocks to the advanced high temperature reactors (AHTRs) as a coolant of liquid-salt Flibe. The neutronic performance of S&B fuel blocks, such as initial multiplication factor, average conversion ratio and discharge burnup, has been investigated by DRAGON V4 using the method of characteristics (MOC) in order to analyze the effects of thorium content and spatial separation. The parameter, absorption ratio of thorium and uranium, is used to quantitatively characterize the spatial separation degree of thorium and uranium, which makes the analysis of spatial separation available. A modified four-factor formula has been proposed and used to analyze the influence of thorium content and spatial separation on initial multiplication factor. With the increase of thorium content or spatial separation degree, the initial multiplication factor decreases due to the more thermal neutron absorbed by thorium. A simplified analysis of conversion ratio shows that it increases with the increase of thorium content for the superior breeding capacity of thorium. The spatial separation can strengthen this advantage when thorium content is more than 60 wt%, otherwise, weaken. Using initial multiplication factor and conversion ratio, the influence of thorium content and spatial separation on discharge burnup can be explained. With the increase of thorium content or spatial separation degree, the effect of the increase of conversion ratio contributes to an increase of discharge burnup. These analysis methods and results are still valid even if the coolant is replaced by helium.
- 出版日期2016-7
- 单位哈尔滨工程大学
