Analysis of the accident with the coolant discharge into the plasma vessel of the W7-X fusion experimental facility-Reference-Cited by-同舟云学术

Analysis of the accident with the coolant discharge into the plasma vessel of the W7-X fusion experimental facility

Published:2013-06 Issue:5 Volume:88 Page:304-310
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Ušpuras E.,Kaliatka A.,Kaliatka T.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference8 articles.

1. The WENDELSTEIN 7-X Project. http://www.ipp.mpg.de/ippcms/eng/for/projekte/w7x, 2009.

2. Manufacturing of the Wendelstein 7-X divertor and wall protection;Benhard;Fusion Engineering and Design,2005

3. L. Topilski, Consequences of the W7X in-vessel coolant pipe break at baking conditions, Report 1-NBF-T0015, Max-Plank-Institut für Plasma Physik, 2006.

4. Nuclear Safety Analysis Division, RELAP5/MOD3.3 code manual volume V, User's guidelines, NUREG/CR-5535, Information Systems Laboratories, Inc., Idaho, 2001.

5. D. Naujoks, Initial and boundary conditions, Report 1-NBF-T0008.0, Max-Plank-Institut für Plasma Physik, 2006.

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1. Thermal hydraulic responses of the Primary Heat Transfer System of the WCCB blanket to accident cases for CFETR;Fusion Engineering and Design;2017-10

2. Analysis of Ingress of Coolant Accident to the Vacuum Vessel of the W7-X Fusion Experimental Facility;Fusion Science and Technology;2017-05-30

3. Modelling of pressure increase protection system for the vacuum vessel of W7-X device;Fusion Engineering and Design;2016-11

4. Assessment of W7-X plasma vessel pressurisation in case of LOCA taking into account in-vessel components;Fusion Engineering and Design;2015-11

5. Reliability and safety analysis for systems of fusion device;Fusion Engineering and Design;2015-05