基于蒙特卡罗代码的针式超临界二氧化碳反应器慢化剂优化设计与分析

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-31 DOI:10.1115/1.4056772
Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
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引用次数: 0

摘要

摘要:本研究分析了氢化钇(YH2)慢化超临界二氧化碳冷却堆装载引脚型、氧化铍稀释氧化物燃料元件以降低临界富集。研究了YH2对冷却剂空洞反应性的影响,并采用慢化剂分区方案来平整化径向功率分布。YH2作为六角形减速棒被添加到燃料组件的中心。采用连续能量反应堆蒙特卡罗代码(RMC)对堆芯进行了动态截面处理。结果表明,在相同的稀释剂体积分数下,YH2慢化剂增加了热裂变,使岩心的临界富集降低了30%以上。YH2慢化剂显著软化了中子能谱,减少了堆芯空化时的中子泄漏,导致堆芯降压时的正光谱反应性反馈较弱,负泄漏反应性反馈较弱。对于装载uo2的堆芯,YH2提供了较低的负冷却剂空洞反应性,而对于装载稀释剂体积分数小于35%的混合氧化物(MOX)堆芯,光谱反馈更为重要,YH2强烈降低了正冷却剂空洞反应性,使其低于1美元。在外围组件中放置YH2将径向功率峰值因子降低到1.319。研究表明,YH2慢化剂降低了临界富集程度,降低了岩心对空化的敏感性,并通过慢化剂分区作用使单富集岩心径向功率分布趋于平缓。
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Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
Abstract This study analyzed an yttrium hydride (YH2) moderated supercritical carbon dioxide cooled reactor loaded with pin-type, beryllium oxide diluted oxide fuel elements to reduce the critical enrichment. The impact of the YH2 on the coolant void reactivity was studied along with a moderator zoning scheme to flatten the radial power distribution. The YH2 was added as hexagonal moderating rods at the center of the fuel assemblies. The core was modeled using the continuous-energy Reactor Monte Carlo code (RMC) with the on-the-fly cross sections treatment. The results showed that the YH2 moderator increased the thermal fission and reduced the critical enrichment of the core with the same diluent volume fraction by more than 30%. The YH2 moderator significantly softened the neutron energy spectrum and reduced the neutron leakage upon core voiding, resulting in both a weaker positive spectral reactivity feedback and a weaker negative leakage reactivity feedback during core depressurization. For an UO2-loaded core, the YH2 gave a lower negative coolant void reactivity, while for a mixed oxide fuel (MOX)-loaded core with diluent volume fractions smaller than 35%, the spectral feedback was more important and the YH2 strongly reduced the positive coolant void reactivity to less than $1. Arranging the YH2 in the peripheral assemblies reduced the radial power peaking factor to 1.319. The study shows that the YH2 moderator can reduce the critical enrichment, make the core less sensitive to voiding, and can flatten the radial power distribution of a single-enrichment core through moderator zoning.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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