Thermal transient computation for a CTR blanket following a major plasma disruption
This study concerns a neutronic and transient thermal study of the first wall and blanket region of a typical controlled thermonuclear reactor (CTR). Previous studies assumed a neutron wall loading of 1 ~ 5 MW/m², and usually an infinite slab for a blanket region in calculating the transient therm...
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| Format: | Others |
| Language: | en_US |
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Virginia Polytechnic Institute and State University
2017
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| Online Access: | http://hdl.handle.net/10919/76579 |