Present status of high-temperature Engineering Test Reactor (HTTR) program

Journal Article · Sat Dec 31 04:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:182026

Tanaka, T; Baba, O; Shiozawa, S ^[1]

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1. Japan Atomic Energy Research Institute, Ibaraki-ken (Japan)

The 30MWt HTTR is a high-temperature gas-cooled reactor(HTGR), with a maximum helium coolant temperature of 950{degrees}C at the reactor outlet. The construction of the HTTR started in March 1991, with first criticality to be followed in 1998 after commissioning testing. At present the HTTR reactor building and its containment vessel have been almost completed and its main components, such as a reactor pressure vessel (RPV), an intermediate heat exchanger, hot gas pipings and graphite core structures, are now manufacturing at their factories aiming at their installation starting in the middle of 1994. The project is intended to establish and upgrade the technology basis necessary for HTGR developments. Japan Atomic Energy Research Institute (JAERI) also plans to conduct material and fuel irradiation tests as an innovative basic research after attaining rated power and coolant temperature. This paper describes major features of HTTR, present status of its construction and research and test program using HTTR.

• OSTI ID: 182026
• Report Number(s): CONF-940501--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: Suppl.1 Vol. 70; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONSTRUCTION
CONTAINMENT
CRITICALITY
DIAGRAMS
FUEL ELEMENTS
HTTR REACTOR
JAERI
PERFORMANCE TESTING
REACTOR COMPONENTS