Assessment of W7-X plasma vessel pressurisation in case of LOCA taking into account in-vessel components
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference7 articles.
1. Wendelstein 7-X—status of the project and commissioning planning;Gasparotto;Fusion Eng. Des.,2014
2. Analysis of the consequences of targets feeding pipe rupture in Wendelstein 7-X experimental nuclear fusion device;Kaliatka,2010
3. Analysis of the accident with the coolant discharge into the plasma vessel of the W7-X fusion experimental facility;Ušpuras;Fusion Eng. Des.,2013
4. Adaptation of the ASTEC code system to accident scenarios in fusion installations;Séropian;Fusion Eng. Des.,2013
5. COCOSYS: status of development and validation of the German containment code system;Allelein;Nucl. Eng. Des.,2008
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. Thermal hydraulic analysis of in-vessel loss of coolant accident for the EAST lower divertor primary heat transfer system;Fusion Engineering and Design;2024-09
2. Thermal Hydraulic Analysis of In-Vessel Loca for the East Lower Divertor Primary Heat Transfer System;2024
3. Analysis of Ingress of Coolant Accident to the Vacuum Vessel of the W7-X Fusion Experimental Facility;Fusion Science and Technology;2017-05-30
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