Tritium Formation and Mitigation in High-Temperature Reactor Systems

Piyush Sabharwall ; Carl Stoots ; Hans A. Schmutz

关键词: High Temperature Reactor;    HTGR;    Molten Salt Reactor;    MSR;   

DOI  :  10.2172/1072395
RP-ID  :  INL/EXT-12-26758
PID  :  OSTI ID: 1072395

学科分类：工程和技术（综合）

美国|英语

来源: SciTech Connect

【 摘 要 】

Tritium is a radiologically active isotope of hydrogen. It is formed in nuclear reactors by neutron absorption and ternary fission events and can subsequently escape into the environment. To prevent the tritium contamination of proposed reactor buildings and surrounding sites, this study examines the root causes and potential mitigation strategies for permeation of tritium (such as: materials selection, inert gas sparging, etc...). A model is presented that can be used to predict permeation rates of hydrogen through metallic alloys at temperatures from 450???750 degrees C. Results of the diffusion model are presented for a steady production of tritium