INVESTIGATION ON THERMAL-FLOW CHARACTERISTICS OF HTGR CORE USING THERMIX-KONVEK MODULE AND VSOP'94 CODE
The failure of heat removal system of water-cooled reactor such as PWR in Three Mile Islands and Fukushima Daiichi BWR makes nuclear society starting to consider the use of high temperature gas-cooled reactor (HTGR). Reactor Physics and Technology Division – Center for Nuclear Reactor Safety and Tec...
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| Format: | Article |
| Language: | English |
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Badan Tenaga Nuklir Nasional (BATAN)
2015-03-01
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| Series: | Tri Dasa Mega |
| Online Access: | http://jurnal.batan.go.id/index.php/tridam/article/view/2236 |