中子能谱对压水堆慢化剂温度系数的影响分析

Analysis of Moderator Temperature Coefficient With Neutron Spectrum for Pressurized Water Reactor

  • 摘要: 在压水堆中,水铀比和235U富集度是影响中子能谱分布的重要参数。本工作在不同水铀比、235U富集度下分析两群中子能谱随燃耗的变化。利用中子能谱分布对慢化剂温度系数的变化进行分析,结果表明:在给定235U富集度条件下,随着水铀比的变化,堆芯存在一慢化剂温度系数绝对值最大值;235U富集度的增加、燃耗的加深,不一定导致慢化剂温度系数绝对值增大。

     

    Abstract: In pressurized water reactor, the H2O/U ratio and 235U enrichment are important parameters affecting the distribution of neutron spectrum. The variation of two-group neutron spectra with burnup was analyzed under the different H2O/U ratios and 235U enrichments. The moderator temperature coefficient was analyzed by using neutron spectrum. The results show that the core has a minimum moderator temperature coefficient with H2O/U ratio change at given 235U enrichment condition, and the increase of 235U enrichment and burnup may not lead to more negative for moderator temperature coefficient.

     

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