Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code-Reference-Cited by-同舟云学术

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Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code

Published:2024-09 Issue: Volume:40 Page:101703
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Zhao Xueli,Yang Wanhuan,Chen Lei^ORCID,Liu Songlin,Xu Bai-Chuan,Li Xiao-Chun^ORCID

Publisher

Elsevier BV

Reference24 articles.

1. Tritium transport analysis for CFETR WCSB blanket

2. Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR;Liu;Theor. Appl. Mech. Lett.,2019

3. Anthropogenic tritium: inventory, discharge, environmental behavior and health effects;Nie;Renew. Sustain. Energy Rev.,2021

4. Development of a Component-Level Hydrogen Transport Model with OpenFOAM and Application to Tritium Transport Inside a DEMO HCPB Breeder;Pasler;Appl. Sci.,2021

5. Tritium transport model at breeder unit level for WCLL breeding blanket;Candido;Fusion Eng. Des.,2019

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