Tritium Formation and Mitigation in High-Temperature Reactor Systems

Sabharwall, Piyush ; Stoots, Carl ; Schmutz, Hans A.

Idaho National Laboratory

关键词: Molten Salt Reactor;    Msr;    High Temperature Reactor;    Htgr;    42 Engineering High Temperature Reactor;   

DOI  :  10.2172/1072395
RP-ID  :  INL/EXT-12-26758
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1072395

美国|英语

来源: UNT Digital Library

【 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