Design and present status of high-temperature engineering test reactor

Conference · Mon Jul 01 04:00:00 EDT 1996

OSTI ID:248164

Baba, Osamu; Kunitomi, Kazuhiko; Kawaji, Satoshi; Tanaka, Toshiyuki; Shiozawa, Shusaku; Okubo, Minoru ^[1]

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1. Japan Atomic Energy Research Inst., Ibaraki (Japan). Dept. of HTTR Project

The Japan Atomic Energy commission (JAEC) decided to construct the high-Temperature engineering Test Reactor (HTTR) in 1987 for establishing and upgrading the basic technologies for advanced HTGRs and serving an irradiation test facility for research in high temperature technologies. The HTTR is a graphite-moderated and helium-gas-cooled test reactor with thermal output of 30MW and inlet and maximum outlet coolant temperature of 395 C and 950 C respectively. Construction started in March 1991 at Oarai site of the Japan Atomic Energy Research Institute (JAERI), with its first criticality at the end of 1997 to be followed after a series of functional tests of half a year. Fabrication of reactor pressure vessel, an intermediate heat exchanger (IHX), gas circulators and other main cooling components has been finished in their factories and installed to the site in 1994. At present, the construction of HTTR reactor building and installation of containment vessel, main and auxiliary cooling systems, etc. are almost completed. This paper describes design of the HTTR reactor cooling system, control system and present status of the HTTR construction.

• OSTI ID: 248164
• Report Number(s): CONF-960306--; ISBN 0-7918-1226-X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONSTRUCTION
DEMONSTRATION PROGRAMS
DESIGN
HEAT EXCHANGERS
HTTR REACTOR
PROCESS HEAT
PROCESS HEAT REACTORS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR TECHNOLOGY