CAJ | 학술논문

在压水堆中，水铀比和235 U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、235 U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235 U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；235 U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。
재압수퇴중，수유비화235 U부집도시영향중자능보분포적중요삼수。본공작재불동수유비、235 U부집도하분석량군중자능보수연모적변화。이용중자능보분포대만화제온도계수적변화진행분석，결과표명：재급정235 U부집도조건하，수착수유비적변화，퇴심존재일만화제온도계수절대치최대치；235 U부집도적증가、연모적가심，불일정도치만화제온도계수절대치증대。
In pressurized water reactor , the H2 O/U ratio and 235 U enrichment are important parameters affecting the distribution of neutron spectrum .The variation of two-group neutron spectra with burnup was analyzed under the different H2 O/U ratios and 235 U enrichments . The moderator temperature coefficient was analyzed by using neutron spectrum . T he results show that the core has a minimum moderator temperature coefficient with H2 O/U ratio change at given 235 U enrichment condition , and the increase of 235 U enrichment and burnup may not lead to more negative for moderator temperature coefficient .