Development of preservation technology for high temperature gas-cooled reactor

Furusawa, Takayuki ; Homma, Fumitaka; Inoi, Hiroyuki; Sawahata, Hiroaki ; Nemoto, Takahiro; Watanabe, Shuji; Ota, Yukimaru

Japan Atomic Energy Agency has constructed the HTTR (High Temperature engineering Test Reactor), which is the Japan's first High Temperature Gas-cooled Reactor (HTGR). The HTTR achieved the full power of 30MW and reactor outlet coolant temperature of 950 $^{circ}$ C on April 19, 2004. Based on the HTTR maintenance experiences, the preservation technology for HTGR are developed. This paper describes its preservation philosophy and typical developed technologies.

Language	:	Japanese
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Meeting title	:	日本保全学会第5回学術講演会
Held date	:	2008/07
Location (city)	:	水戸
Location (country)	:	日本
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Keywords	:	no keyword
Research Facility	:	HTTR(高温工学試験研究炉)
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Registration No. : BB20080643
JAEA Abstracts No. :
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