Tritium storage and release mechanism in nuclear graphite using first-principles combined thermal desorption theory-Reference-Cited by-同舟云学术

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Tritium storage and release mechanism in nuclear graphite using first-principles combined thermal desorption theory

Published:2024-04 Issue: Volume:223 Page:119012
ISSN:0008-6223
Container-title:Carbon
language:en
Short-container-title:Carbon

Author:

Zhou Ziling^ORCID,Nie Rui,Wang Yu^ORCID,Guo Jingni,Wei Liqiang^ORCID,Xie Feng^ORCID,Cao Jianzhu,Dong Yujie^ORCID,Wen Yanwei,Shan Bin

Publisher

Elsevier BV

Reference97 articles.

1. Tritium content and chemical form in nuclear graphite from molten fluoride salt irradiations;Dolan;Fusion Sci. Technol.,2020

2. Tritium control and capture in salt-cooled fission and fusion reactors: status, challenges, and path forward;Forsberg;Nucl. Technol.,2017

3. Kinetics and transport of hydrogen in graphite at high temperature and the effects of oxidation, irradiation and isotopics;Vergari;J. Nucl. Mater.,2022

4. Tritium balance in high-temperature gas-cooled reactors;Rohrig;J. Am. Ceram. Soc.,1976

5. Thermodynamics of hydrogen in graphite at high temperature and the effects of oxidation, irradiation and isotopics;Vergari;J. Nucl. Mater.,2021

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