Analysis of Calculation Codes for Metal Tritium Interaction and Numerical Evaluation of the Tritium Behaviour in the Net First Wall
Author:
Affiliation:
1. Commission of the European Communities, Joint Research Centre - Ispra Establishment, 21020 Ispra (Va) - Italy, (0039-332) 789209
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST85-A24633
Reference11 articles.
1. Tritium permeation and wall loading in the TFTR vacuum vessel
2. A calculation of the surface recombination rate constant for hydrogen isotopes on metals
3. Hydrogen recycling properties of stainless steels
4. A simple theory for maximum h inventory and release: A new transport parameter
Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Mistral: A comprehensive model for tritium transport in lithium-base ceramics;Journal of Nuclear Materials;1990-09
2. Tritium recycling, permeation and inventory in a self-cooled fusion reactor blanket using Pb17Li or Flibe as a breeder and V or Fe as a first wall material;Vacuum;1989-01
3. The Impact of Tritium Solubility and Diffusivity on Inventory and Permeation in Liquid Breeder Blankets;Fusion Technology;1988-09
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