The issue of Tritium in DEMO coolant and mitigation strategies
Author:
Funder
Euratom Research and Training Programme
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference24 articles.
1. Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor
2. Tritium management in HCLL-PPCS model AB blanket
3. Tritium Migration in HCLL and WCLL Blankets: Impact of Tritium Solubility in Liquid Pb-17Li
4. Tritium management and anti-permeation strategies for three different breeding blanket options foreseen for the European Power Plant Physics and Technology Demonstration reactor study
5. Solubility and diffusivity of hydrogen isotopes in liquid Pb17Li
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