Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design
Handling of a large thermal power exhausted from the confined plasma is one of the most important issues for ITER and DEMO. A conventional divertor, which has the closed geometry similar to that of ITER and longer leg of 1.6 m, was proposed for the Japanese (JA) DEMO reactor (Rp/ap = 8.5/2.42 m). A...
Main Authors: | N. Asakura, K. Hoshino, Y. Homma, Y. Sakamoto |
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Format: | Article |
Language: | English |
Published: |
Elsevier
2021-03-01
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Series: | Nuclear Materials and Energy |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179120301319 |
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