“华龙一号”MOX燃料再循环方案可行性研究  

Feasibility Study on MOX Fuel Recirculation Scheme of HPR1000

作　　者：饶倩蓝 李柏良 吉文浩 秦雪 李晴 肇博涛 包煜轩 霍明庆 RAO Qianlan;LI Bailiang;JI Wenhao;QIN Xue;LI Qing;ZHAO Botao;BAO Yuxuan;HUO Mingqing(CNNC Long'an Co.,Ltd.Beijing 100036,China;Nuclear Power Institute of China,Chengdu 610213,China;Institute of Beijing Nuclear Chemical Research and Design,China Nuclear Power Engineering Co.,Ltd.Beijing 100048,China)

机构地区：[1]中核龙安有限公司,北京610213 [2]中国核动力研究设计院,成都610213 [3]中国核电工程有限公司北京核化工研究设计院,北京100048

出　　处：《现代应用物理》2024年第3期83-88,104,共7页Modern Applied Physics

基　　金：中核龙安有限公司自主科研基金资助项目(LA-BUD-CT-CM-00112)。

摘　　要：针对堆后铀和分离钚在压水堆中的复用问题提出以“华龙一号”为应用目标的热堆铀钚混合氧化物(mixed oxide fuel,MOX)燃料再循环方案,设计了与“华龙一号”现用UO_(2)燃料组件等效的2种不同平均钚质量分数的MOX燃料组件,提出了MOX燃料组件中燃料棒的布置方案。进一步提出了“华龙一号”装载30%MOX燃料组件的堆芯管理方案,并通过计算验证了方案的可行性。计算结果表明,装载MOX燃料的反应堆慢化剂温度系数、停堆裕量、核焓升因子、热点因子、循环长度等关键参数均能满足“华龙一号”设计限值要求,证明在“华龙一号”堆芯中装载30%的MOX燃料组件是基本可行的。To address the reuse of post-reactor uranium and separated plutonium in pressurized water reactors,a mixed oxide fuel(MOX) recycling scheme for thermal reactors targeting HPR1000 is proposed.Two types of MOX fuel assemblies with different average plutonium mass fractions,equivalent to the UO_(2) fuel assembly currently used in HPR1000,are designed and the arrangement of fuel rods in MOX fuel assemblies is proposed.A reactor core management strategy for the integration of 30% MOX fuel assemblies into the HPR1000 reactor core is further proposed,and its feasibility is verified by calculations.The calculated results show that the key parameters,including the reactor moderator temperature coefficient,shutdown margin,nuclear enthalpy rise factor,hot spot factor,and cycle length,all adhere to the stringent design limits set for HPR1000.These findings substantiate the assertion that the proposed scheme of incorporating 30% MOX fuel assemblies into the coefficient core is fundamentally feasible.

关 键 词：核燃料闭式循环 堆后铀钚应用 MOX燃料 热堆循环 “华龙一号” 

分 类 号：TL249[核科学技术—核燃料循环与材料] O571[理学—粒子物理与原子核物理]