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Research Papers

Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor

[+] 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,
Higashi-ibaraki-gun,
Oarai 311-1393, Ibaraki, Japan
e-mail: 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,
Higashi-ibaraki-gun,
Oarai 311-1393, Ibaraki, Japan
e-mail: 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,
Higashi-ibaraki-gun,
Oarai 311-1393, Ibaraki, Japan
e-mail: 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,
Higashi-ibaraki-gun,
Oarai 311-1393, Ibaraki, Japan
e-mail: 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,
Higashi-ibaraki-gun,
Oarai 311-1393, Ibaraki, Japan
e-mail: 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,
Higashi-ibaraki-gun,
Oarai 311-1393, Ibaraki, Japan
e-mail: takada.shoji@jaea.go.jp

Manuscript received September 29, 2016; final manuscript received June 1, 2017; published online July 31, 2017. Assoc. Editor: Guoqiang Wang.

ASME J of Nuclear Rad Sci 3(4), 041013 (Jul 31, 2017) (8 pages) Paper No: NERS-16-1123; doi: 10.1115/1.4036985 History: Received September 29, 2016; Revised June 01, 2017

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 (PCS) 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 temperature decrease of RPV was several degrees during the test. The numerical result showed a good agreement with the test result of temperature rise of biological shielding concrete around 1 °C by the numerical method that uses a calibrated thermal resistance by using the measured temperatures of RPV and the air outside of biological shielding concrete. The temperature increase of water cooling tube panel of VCS was calculated to be about 15 °C which is sufficiently small in the view point of property protection. It was confirmed that the sufficient cooling capacity of VCS can be maintained even in case that one of two water cooling lines of VCS loses its function.

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References

Figures

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Fig. 1

Reactor core structure of HTTR

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Fig. 2

Fuel assembly of HTTR

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Fig. 3

Cooling system of HTTR

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Fig. 5

Schematic drawing of VCS

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Fig. 6

Schematic drawing of horizontal cross section model

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Fig. 7

Detail drawing of horizontal cross section model

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Fig. 8

The test results of the time history of normalized mass flow rate and normalized reactor power after helium gas circulators stopped

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Fig. 9

The time history of various parameters after helium gas circulators stopped: (a) numerical result of water cooling tube panel of VCS, (b) test and numerical results of biological shielding concrete (side), (c) test result of biological shielding concrete (upper), (d) test result of RPV, and (e) test result of permanent reflector block

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