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Title: Tritium Formation and Mitigation in High-Temperature Reactor Systems

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
Authors:
; ;
Publication Date:
OSTI Identifier:
1072395
Report Number(s):
INL/EXT-12-26758
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING High Temperature Reactor; HTGR; Molten Salt Reactor; MSR