摘要：燃料组件在反应堆内受压紧力等作用会发生弯曲,该弯曲会显著改变反应堆局部位置的中子慢化。基于中广核核设计软件包PCM中的组件中子截面计算软件PINE和堆芯核设计软件COCO,开发了专门的燃料组件弯曲模型,以分析燃料组件弯曲对堆芯局部功率分布的影响,并和蒙特卡罗软件JMCT做了对比验证计算。计算结果表明,PCM软件包燃料组件弯曲模型的计算结果与JMCT吻合良好,该软件包可以用于燃料组件弯曲的分析计算。燃料组件的弯曲对于堆芯的局部功率分布有显著的影响,需要在设计中予以特别关注。

摘要：REMIX燃料是利用乏燃料后处理中回收的未分离铀、钚混合物直接生产而成的。REMIX乏燃料可以重新回收利用,形成闭式循环,从而减少放射性废物的产生量。本文旨在讨论REMIX燃料组件在CPR1000型反应堆中的适用性,计算采用SCIENCE V2程序包,基于CPR1000型核反应堆18个月换料设计,全堆芯使用REMIX燃料进行平衡循环燃料管理方案设计,并将通用核数据和关键中子学参数与工程设计限值进行了对比。结果显示,REMIX堆芯燃料管理方案能够满足堆芯各项核设计参数安全限值与设计限值,其各项关键中子学参数能被当前UO2堆芯的安全分析限值所包络。本文从核设计的角度初步论证了REMIX燃料在CPR1000机组中应用的可行性。REMIX fuel is produced directly from a mixture of the unseparated uranium and plutonium recovered from spent fuel reprocessing. REMIX spent fuel can be recycled to form a closed loop, thus reducing the quantity of radioactive waste generated. The purpose of this article is to discuss the feasibility of REMIX fuel compositions in CPR1000 reactor. The calculations are practiced with SCIENCE V2 Package, based on an 18-month refueling design of CPR1000 nuclear reactor with a balanced-cycle full management scheme design using REMIX fuel for the entire core. The general nuclear data and key neutronic parameters are compared to the engineering design limits. The results show that the REMIX core fuel management scheme is able to meet the safety and design limits for all nuclear design parameters of the core, and its key neutronic parameters can be enveloped by the current safety analysis limits applied for UO2 fuel. This paper preliminarily demonstrates the feasibility of applying REMIX fuel in CPR1000 units in terms of nuclear design.