Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water-Cooled Blanket, for the Purpose of the Preconceptual Design
Author:
Affiliation:
1. Department of Astronautical, Electrical and Energy Engineering, Nuclear Section, Sapienza, University of Rome, C.so Vittorio Emanuele II, 244-00186 Rome, Italy
Abstract
Publisher
Hindawi Limited
Subject
Nuclear Energy and Engineering
Link
http://downloads.hindawi.com/journals/stni/2016/8719695.pdf
Reference10 articles.
1. Fusion Licensing and Safety Studies in Korea
2. Overview of EU DEMO design and R&D activities
3. Preliminary Analysis of In-Vessel First Wall Cooling Pipe Ruptures for ITER
4. Thermohydraulic Analysis of Accident Scenarios of a Fusion DEMO Reactor Based on Water-Cooled Ceramic Breeder Blanket: Analysis of LOCAs and LOVA
5. Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors
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