Neutronics calculations and characteristic study of the HTTR high temperature test reactor core
碩士 === 國立清華大學 === 工程與系統科學系 === 101 === The high temperature test reactor (HTTR) in Japan is a 30 MW thermal, graphite-moderated, helium-cooled reactor that was built to demonstrate the technological feasibility and advantages of one of the GEN-IV reactors, i.e. the prismatic-type very high temperatu...
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| Format: | Others |
| Language: | zh-TW |
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2012
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| Online Access: | http://ndltd.ncl.edu.tw/handle/20809155037079499561 |