摘要
N36合金是我国自主研发的先进锆合金,将作为华龙一号反应堆燃料元件的包壳材料。为了研究N36合金包壳的堆内性能,验证其用于燃料元件包壳的可行性,以N36合金为包壳设计了N36合金特征化燃料组件,在秦山二期核电厂反应堆内进行了辐照考验,并在每循环末通过池边检查获取堆内性能数据,基于堆内数据对N36合金包壳的性能进行了分析和评价。本文研究提供了N36合金特征化燃料的辐照考验方案、N36合金特征化燃料的设计、堆内性能数据的获取方式以及N36合金与Zr-4合金堆内性能对比结果。
N36, a kind of advanced zirconium alloy developed independently in China, will be adopted as the cladding material of fuel assembly in HPR1000. In order to study the N36 alloy cladding performance in a reactor and verify the feasibility of using this alloy for cladding, the N36 characteristic fuel assembly with the N36 alloy cladding is designed and loaded in the reactor of Qinshan NPP Phase Ⅱ for irradiation test. The pool side examination is performed at the end of each cycle to collect the in-core performance data of this fuel assembly. Then, the performance of N36 alloy cladding is analyzed and evaluated based on these data. For this sake, this study provides the irradiation test scheme, design and in-core performance collection method of the N36 characteristic fuel, and compares the in-core performance of N36 alloy and Zr-4 alloy.
作者
张坤
陈平
邢硕
庞华
彭航
蒲曾坪
何梁
张林
秋博文
Zhang Kun;Chen Ping;Xing Shuo;Pang Hua;Peng Hang;Pu Zengping;He Liang;Zhang Lin;Qiu Bowen(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2021年第5期110-113,共4页
Nuclear Power Engineering
基金
国家自然科学基金(U1867219)。
关键词
N36合金
特征化燃料
池边检查
性能分析
N36 alloy
Characteristic fuel assembly
Pool side examination
Performance analysis
