CAJ | 학술논문

使用MOX燃料的快堆核电站以其线功率高、燃耗高、堆芯出口温度高等特点,对堆芯热工设计提出了新的问题.本文在对MOX燃料热工性能分析的基础上,给出了主要的热工设计限值,并以电功率870 MW电站为参考,初步分析了其堆芯热工特性和设计裕量.结果表明对于MOX燃料,较高的堆芯热工参数合理可行,且具有足够的裕量.
사용MOX연료적쾌퇴핵전참이기선공솔고、연모고、퇴심출구온도고등특점,대퇴심열공설계제출료신적문제.본문재대MOX연료열공성능분석적기출상,급출료주요적열공설계한치,병이전공솔870 MW전참위삼고,초보분석료기퇴심열공특성화설계유량.결과표명대우MOX연료,교고적퇴심열공삼수합리가행,차구유족구적유량.
For the MOX core of a Sodium-cooled Fast Reactor(SFR) nuclear power plant, the advantages are higher linear power, burn-up and outlet temperature. Core thermal hydraulic design meets some new issues. Based on the analysis of MOX fuel characteristics, the thermal design criteria of core were raised in this paper. Core thermal characteristics and margin were analyzed for the 870 MWe nuclear power plant. The results showed that higher thermal parameters were reasonable and feasible for the MOX core, and the thermal margin satisfied the requirements.