Safety shutdown of the high temperature engineering test reactor during loss of off-site electric power simulation test

Takeshi Takeda, Shigeaki Nakagawa, Fumitaka Honma, Eiji Takada, Nozomu Fujimoto

Research output: Contribution to journalArticle

2 Citations (Scopus)

Abstract

The high temperature engineering test reactor (HTTR) is a graphite-moderated and helium-gas-cooled reactor, which is the first high temperature gas-cooled reactor in Japan. The HTTR achieved its first full power of 30 MW at rated operation on December 7 in 2001. In the rise-to-power test of the HTTR, simulation test of anticipated operational occurrence with scram was carried out by manual shutdown of off-site electric power from 30 MW operation. Because helium circulators and water pumps coasted down immediately after the loss of off-site electric power, mass flow rates of helium and water decreased to the scram points. Sixteen pairs of control rods were inserted at two-steps into the core by gravity within the design criterion of 12 s. In 51 s after the loss of off-site electric power, the auxiliary cooling system started up by supplying electricity from emergency power feeders. In 40 min after the startup of the auxiliary cooling system, one of two auxiliary helium circulators stopped for reducing thermal stresses of core graphite components such as fuel blocks. Temperature of hot plenum block among core graphite structures decreased continuously after the startup of the auxiliary cooling system. Blackout sequences of the HTTR dynamic components were in accordance with the design. As a result of the loss of off-site electric power simulation test, it was confirmed that the HTTR shuts down safely after the scram.

Original languageEnglish
Pages (from-to)986-995
Number of pages10
Journaljournal of nuclear science and technology
Volume39
Issue number9
DOIs
Publication statusPublished - Sep 2002

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engineering test reactors
High temperature engineering
shutdowns
Plant shutdowns
electric power
safety
Helium
cooling systems
Cooling systems
helium
Plant startup
Graphite
graphite
simulation
blackout
gas cooled reactors
high temperature gas cooled reactors
control rods
Gas cooled reactors
Control rods

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

Safety shutdown of the high temperature engineering test reactor during loss of off-site electric power simulation test. / Takeda, Takeshi; Nakagawa, Shigeaki; Honma, Fumitaka; Takada, Eiji; Fujimoto, Nozomu.

In: journal of nuclear science and technology, Vol. 39, No. 9, 09.2002, p. 986-995.

Research output: Contribution to journalArticle

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