超高通量快中子试验堆堆芯初步概念设计  被引量:3

Preliminary Conceptual Design of Ultra-high Flux Fast Neutron Test Reactor Core

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作  者:蔡云[1] 王连杰[1] 汪量子[1] 夏榜样[1] 娄磊[1] 张斌[1] 张策 胡钰莹 Cai Yun;Wang Lianjie;Wang Liangzi;Xia Bangyang;Lou Lei;Zhang Bin;Zhang Ce;Hu Yuying(Science and Technology on Reactor System Design Technology 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

出  处:《核动力工程》2023年第2期222-226,共5页Nuclear Power Engineering

摘  要:针对先进核能系统发展需要,提出了超高通量堆的堆芯概念设计。本文采用板型燃料、正方形燃料组件设计,设置宽流道保证堆芯冷却剂占有较高的体积份额。堆芯采用52盒燃料组件,设置8盒控制棒组件和较厚的反射层。通过堆芯概念设计方案评价,结果表明堆芯循环长度可达100EFPD(等效满功率天),所提出的超高通量堆的最大中子注量率可达到1.08×10^(16)cm^(−2)·s^(−1)。To meet the development need of advanced nuclear systems,an ultra-high flux reactor(UFR)core design concept is proposed in this paper.In this concept,plate-type fuel and square fuel assembly design is adopted,and a wide flow channel is provided to ensure a high volume share of the core coolant.The core is provided with 52 boxes of fuel assemblies,8 boxes of control rod assemblies and a thick reflective layer.The results show that the cycle length of the core can reach 100 equivalent full power days(EFPD)by the core conceptual design scheme evaluation.The maximum neutron fluence rate of the proposed ultra-high flux reactor can reach 1.0×10^(16)cm^(−2)·s^(−1).

关 键 词:超高通量堆 初步概念设计 中子注量率 

分 类 号:TL334[核科学技术—核技术及应用]

 

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