Tritium Formation and Mitigation in High Temperature Reactors

Sabharwall, Piyush ; Stoots, Carl

Idaho National Laboratory

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

DOI  :  10.2172/1060976
RP-ID  :  INL/EXT-12-26758
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1060976

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. In order to prevent the tritium contamination of proposed reactor buildings and surrounding sites, this paper examines the root causes and potential solutions for the production of this radionuclide, including materials selection and inert gas sparging. A model is presented that can be used to predict permeation rates of hydrogen through metallic alloys at temperatures from 450–750°C. Results of the diffusion model are presented for one steadystate value of tritium production in the reactor.