基于MOX燃料组件的177混合堆芯装料方案数值研究  

Numerical Study on 177 Hybrid Core Loading Scheme Based on MOX Fuel Assembly

作　　者：汪宁远 李然 刘义保 杨灵芳 杨波 Wang Ningyuan;Li Ran;Liu Yibao;Yang Lingfang;Yang Bo(East China University of Technology,Nanchang,330013,China;Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]东华理工大学核科学与工程学院,南昌330013 [2]中国核动力研究设计院,成都610213

出　　处：《核动力工程》2018年第4期6-10,共5页Nuclear Power Engineering

基　　金：江西省科技厅推荐项目(20144BDH80011);江西省教育厅科技落地计划项目(KJLD12076)

摘　　要：通过计算华龙一号(HPR1000)压水堆平均卸料燃耗得到乏燃料中钚(Pu)同位素的含量,以此成分比例来设计铀钚混合氧化物(MOX)燃料。采用离散型燃料组件设计,通过不同Pu含量的MOX燃料棒离散型布置来降低与UO2燃料组件间的功率梯度。采用程序MCNP和COSLATC模拟堆芯功率分布和热中子注量率分布,采用分区分层的低泄漏装料方案,降低不同燃料组件间的功率梯度,展平堆芯的功率分布。在不考虑可燃毒物的前提下,利用3种Pu含量的MOX组件将混合堆芯的功率峰因子控制在1.77左右,明显优于原堆芯的功率峰因子,为国产三代压水堆引入MOX燃料提供了具有参考价值的装料方案。Through the calculation of the fuel average discharge burn-up of HPR1000, the isotope of Pu in the spent fuel has been derived, with which composition the MOX fuel shall be designed. Based on the discrete fuel module design, the power gradient with the fuel module of UO2 is reduced through the discrete layout of MOX fuel bar with Pu contents. This paper employs Monte Carlo Program MCNP and COSLATC to simulate the reactor core power distribution and the thermal neutron flux distribution, and uses the compartmentalized and layering loading scheme with low leakage to reduce the power gradient between fuel modules and flatten power distribution of the reactor core. Leaving out burnable poisons, three MOX modules with different Pu contents are used to control the power peak factor of the mixed reactor core at around 1.77, visibly better than the power peak factor of the original reactor core, which serves to provide a scheme of considerable reference value that introduces the MOX fuel for the 3 rd generation of domestically developed pressurized water reactor in China.

关 键 词：MOX燃料组件 华龙一号(HPR1000) 混合堆芯装载方案 

分 类 号：TL327[核科学技术—核技术及应用]