摘要
在燃料元件堆内功率瞬态试验中,为净化氦-3气体吸收中子产生的氚,保证试验的安全性,需设计一个用于捕集氚的装置——氚阱。选择海绵钛作为贮氚金属。原型容器的设计主要依据氚的产量、氚钛化学反应、温度、压力、还有氚衰变氦释放等因素。总体结构采用内加热形式的双层包套式不锈钢压力容器,可减小热损失和氚的渗透量。本文同时也介绍了氚阱的结构、传热、屏蔽和密封等的分析结果。
The purpose of this study is to develop the tritium trap for LWR fuel element irradiation test with power transient, to purify the 3He gas from tritium produced by neutron capture. Titanium sponge particles were selected as the storage materials. The design of prototype vessel was determined by factors such as the amount of tritium, the titanium-hydrogen reaction, the temperature by the electric heat, the maximum possible pressure of 3He, and helium release condition by the decay tritium. The titanium bed was heated internally to reduce the heat loss, and the primary and secondary containments of stainless steel were applied to prevent the permeation of tritium. Analysis results for the structure, heat transfer, shielding, and confinement of this trap are introduced.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2015年第1期77-80,共4页
Nuclear Power Engineering
基金
国家重大科技专项经费资助(2011ZX06004-008)
关键词
氚阱
功率跃增
辐照试验
氦-3回路
Tritium trap, Power ramp, Irradiation test, 3He loop