REMIX燃料在CPR1000反应堆应用的可行性研究
Feasibility Study of REMIX Fuel in CPR1000 Reactor
DOI: 10.12677/nst.2024.124031, PDF,   
作者: 彭靖含, 位金锋*：中广核研究院有限公司，广东 深圳
关键词: REMIX燃料；燃料管理；中子学参数；REMIX Fuel； Fuel Management； Neutronic Parameters
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。
Abstract: 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.
文章引用：彭靖含, 位金锋. REMIX燃料在CPR1000反应堆应用的可行性研究[J]. 核科学与技术, 2024, 12(4): 316-322. https://doi.org/10.12677/nst.2024.124031

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