Coolant chemistry characteristics during safety demonstration test using HTTR

Sakaba, Nariaki ; Nakagawa, Shigeaki ; Furusawa, Takayuki ; Tachibana, Yukio

Carbon deposition occurred occasionally in the graphite-moderated gas-cooled reactors was evaluated for the reactor pressure vessel, intermediate heat exchanger, etc. using the measured chemical impurity data for the initial condition of the safety demonstration test. By the evaluated result, it is confirmed that the high-temperature components keep their structural integrity during the any temperature transients in safety demonstration tests.

Language	:	English
Journal	:	Transactions of the American Nuclear Society
Volume	:	91
Number	:
Pages	:	P. 377
Publication Year/Month	:	2004/00
Meeting title	:	American Nuclear Society 2004 Winter Meeting and Nuclear Technology Expo
Held date	:	2004/11
Location (city)	:	Washington, D.C.
Location (country)	:	U.S.A.
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:
Keywords	:	Structural Integrity Assessment; High Temperature; PPWC; IHX; RPV; Impurity; Carbon Deposit; VHTR; HTTR; HTGR
Research Facility	:	HTTR(高温工学試験研究炉)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	文部科学省

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Registration No. : B20040970
JAEA Abstracts No. :
Paper Submission No. : 486

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