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

被引:3
|
作者
Takeda, T [1 ]
Nakagawa, S [1 ]
Honma, F [1 ]
Takada, E [1 ]
Fujimoto, N [1 ]
机构
[1] Japan Atom Energy Res Inst, Dept HTTR Project, Oarai, Ibaraki 3111394, Japan
关键词
HTGR type reactors; HTTR reactor; rise-to-power test; off-site electric power; simulation; safety shutdown; scram; reactor core; control rods; auxiliary cooling system; reactor shutdown;
D O I
10.3327/jnst.39.986
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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 30MW 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.
引用
收藏
页码:986 / 995
页数:10
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