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中子能谱对压水堆慢化剂温度系数的影响分析 被引量:5

Analysis of Moderator Temperature Coefficient With Neutron Spectrum for Pressurized Water Reactor
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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。 In pressurized water reactor, the H20/U ratio and 23sU enrichment are important parameters affecting the distribution of neutron spectrum. The variation of two-group neutron spectra with burnup was analyzed under the different H20/U ratios and 23sU enrichments. The moderator temperature coefficient was analyzed by using neutron spectrum. The results show that the core has a minimum moderator temperature coefficient with H20/U ratio change at given 235U enrichment condition, and the increase of 23sU enrichment and burnup may not lead to more negative for moderator temperature coefficient.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第9期1594-1598,共5页 Atomic Energy Science and Technology
关键词 中子能谱 富集度 水铀比 慢化剂温度系数 neutron spectrum enrichment H2O/U ratio moderator temperature coefficient
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参考文献3

  • 1OI N, SUKHANOV G, HESKETH K, et al. Impact of extended burnup on the nuclear fuel cycle[C]// Proceedings of an Advisory Group Meeting. Vienna: Fs. n. 1, 1991.
  • 2BERTEL E, NORDBORG C, LEE K S, et al. Very high burn-ups in light water reactors[R]. Paris: OECD/NEA, 2006.
  • 3XU Zhiwen. Design strategies for optimizing high burnup fuel in pressurized water reactors [D]. USA: Massachusetts Institute of Technolo- gy, 2003.

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