超高通量快中子研究堆核燃料概念设计研究  

Conceptual Design Study of Ultra-high Flux Fast Neutron Research Reactor Fuel

作　　者：李文杰[1] 夏榜样[1] 余红星[1] 焦拥军[1] 李权[1] 孙丹 吴裕[2] Li Wenjie;Xia Bangyang;Yu Hongxing;Jiao Yongjun;Li Quan;Sun Dan;Wu Yu(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;Science and Technology on Nuclear Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213 [2]中国核动力研究设计院核燃料与材料技术重点实验室,成都610213

出　　处：《核动力工程》2022年第6期217-221,共5页Nuclear Power Engineering

基　　金：中国核动力研究设计院原创基金创新团队项目(KJCX-2021-TD-02)。

摘　　要：提高中子注量率是高通量研究堆的发展趋势,能够大幅加速反应堆材料研发进程。但若提高中子注量率至10^(16)cm^(−2)·s^(−1)将导致功率密度峰值相较于现有研究堆高数倍,对反应堆和核燃料设计带来许多挑战。为此,本文从中子学、传热、燃料材料堆内行为等方面半定量分析了提高中子注量率对核燃料性能的影响,并提出应对超高通量和功率密度挑战的设计措施,为发展超高通量快中子研究堆燃料设计提供指导。Increasing neutron fluence rate is the development trend of high flux research reactor,which can greatly accelerate the R&D process of reactor materials.However,if the neutron fluence rate is increased to 10^(16)cm^(−2)·s^(−1),the peak power density will be several times higher than that of the existing research reactor,which will bring many challenges to the reactor and nuclear fuel design.For this reason,this paper semi quantitatively analyzes the impact of increasing neutron fluence rate on the performance of nuclear fuel from neutronics,heat transfer,fuel material behavior in the reactor and other aspects,and proposes design measures to meet the challenges of ultra-high flux and power density,providing guidance for the development of ultra-high flux fast neutron research reactor fuel design.

关 键 词：超高通量 研究堆 核燃料 传热 设计 

分 类 号：TL334[核科学技术—核技术及应用]