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Loss of core cooling test with one cooling line inactive in Vessel Cooling System (VCS) of High Temperature Engineering Test Reactor (HTTR)

[+] Author and Article Information
Yusuke Fujiwara

HTTR Reactor Engineering Section, Department of HTTR, Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency Oarai, Higashi-ibaraki-gun, Ibaraki, Japan
fujiwara.yusuke@jaea.go.jp

Takahiro Nemoto

HTTR Operation Section, Department of HTTR, Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency Oarai, Higashi-ibaraki-gun, Ibaraki, Japan
nemoto.takahiro44@jaea.go.jp

Daisuke Tochio

HTTR Reactor Engineering Section, Department of HTTR, Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency Oarai, Higashi-ibaraki-gun, Ibaraki, Japan
tochio.daisuke@jaea.go.jp

Masanori Shinohara

HTTR Project Management Section, Department of HTTR, Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency Oarai, Higashi-ibaraki-gun, Ibaraki, Japan
shinohara.masanori@jaea.go.jp

Masato Ono

HTTR Reactor Engineering Section, Department of HTTR, Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency Oarai, Higashi-ibaraki-gun, Ibaraki, Japan
ono.masato@jaea.go.jp

Shoji Takada

HTTR Reactor Engineering Section, Department of HTTR, Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency Oarai, Higashi-ibaraki-gun, Ibaraki, Japan
takada.shoji@jaea.go.jp

1Corresponding author.

ASME doi:10.1115/1.4036985 History: Received September 29, 2016; Revised June 01, 2017

Abstract

In the High Temperature Engineering Test Reactor (HTTR), the Vessel Cooling System (VCS) which is arranged around the reactor pressure vessel (RPV) removes residual heat and decay heat from the reactor core when the forced core cooling is lost. The test of loss of forced cooling (LOFC) when one of two cooling lines in VCS lost its cooling function was carried out to simulate the partial loss of cooling function from the surface of RPV using the HTTR at the reactor thermal power of 9 MW, under the condition that the reactor power control system and the reactor inlet coolant temperature control system were isolated, and three helium gas circulators (HGCs) in the primary cooling system were stopped. The test results showed that the reactor power immediately decreased to almost zero, which is caused by negative feedback effect of reactivity, and became stable as soon as HGCs were stopped. On the other hand, the temperature changes of permanent reflector block, RPV and the biological shielding concrete were quite slow during the test. The numerical result showed a good agreement with the test result of temperature rise of biological shielding concrete around 1 °C. The temperature increase of water cooling tube panel of VCS was calculated about 15 °C which is sufficiently small in the view point of property protection. As the results, it was confirmed that the cooling capacity of VCS can be kept sufficiently even in case that one of two water cooling lines of VCS loses its function.

Copyright (c) 2017 by ASME
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