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Research Papers

Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR

[+] Author and Article Information
Yoshitomo Inaba

Small-Sized HTGR Research and Development Division, HTGR Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: inaba.yoshitomo@jaea.go.jp

Kenji Sekita

Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: sekita.kenji@jaea.go.jp

Takahiro Nemoto

Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: nemoto.takahiro44@jaea.go.jp

Yuki Honda

Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: honda.yuki@jaea.go.jp

Daisuke Tochio

Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: tochio.daisuke@jaea.go.jp

Hiroyuki Sato

Small-Sized HTGR Research and Development Division, HTGR Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: sato.hiroyuki09@jaea.go.jp

Shigeaki Nakagawa

Small-Sized HTGR Research and Development Division, HTGR Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: nakagawa.shigeaki@jaea.go.jp

Shoji Takada

Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: takada.shoji@jaea.go.jp

Kazuhiro Sawa

Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393, Japan e-mail: sawa.kazuhiro@jaea.go.jp

1Corresponding author.

Manuscript received September 25, 2015; final manuscript received July 22, 2016; published online October 12, 2016. Assoc. Editor: Asif Arastu.

ASME J of Nuclear Rad Sci 2(4), 041001 (Oct 12, 2016) (7 pages) Paper No: NERS-15-1194; doi: 10.1115/1.4034320 History: Received September 25, 2015; Accepted July 22, 2016

The nuclear heat utilization systems connected to high-temperature gas-cooled reactors (HTGRs) will be designed on the basis of non-nuclear-grade standards in terms of easier entry for the chemical plant companies and the construction economics of the systems. Therefore, it is necessary that the reactor operations can be continued even if abnormal events occur in the systems. The Japan Atomic Energy Agency has developed a calculation code to evaluate the absorption of thermal-load fluctuations by the reactors when the reactor operations are continued after such events, and has improved the code based on the high-temperature engineering test reactor (HTTR) operating data. However, there were insufficient data on the transient temperature behavior of the metallic components and the graphite core support structures corresponding to the fluctuation of the reactor inlet coolant temperature for further improvement of the code. Thus, nuclear heat supply fluctuation tests with the HTTR were carried out in non-nuclear heating operation to focus on the thermal effect. In the tests, the coolant helium gas temperature was heated to 120°C by the compression heat of the gas circulators in the HTTR, and a sufficiently large fluctuation of 17°C for the reactor inlet coolant was achieved by devising a new test procedure under the ideal condition without the effect of the nuclear power. Then, the temperature responses of the metallic components and the graphite core support structures were investigated. The test results adequately showed as predicted that the temperature responses of the metallic components are faster than those of the graphite blocks, and the mechanism of the thermal-load fluctuation absorption by the metallic components was clarified.

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References

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Figures

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Fig. 1

Whole constitution diagram of HTTR

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Fig. 2

Cutaway view of reactor pressure vessel and core of HTTR

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Fig. 3

Test procedure of non-nuclear heating tests with HTTR

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Fig. 4

Proposed new test procedure for case 1

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Fig. 5

Temperature responses of helium gas, pressurized water, and reactor internals for preliminary test: (a) normalized temperatures of pressurized water, reactor inlet and outlet coolant and (b) normalized temperatures of reactor internals

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Fig. 6

Temperature responses of helium gas, pressurized water, and reactor internals for case 1: (a) normalized temperatures of pressurized water, reactor inlet and outlet coolant and (b) normalized temperatures of reactor internals

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Fig. 7

Thermal disturbance absorptions by reactor internals against temperatures of reactor inlet, reactor outlet, and core inlet coolant for case 1: (a) normalized temperatures of core inlet coolant, reactor inlet and outlet coolant and (b) normalized thermal disturbance absorption by reactor internals

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Fig. 8

Temperature responses of helium gas, pressurized water, and reactor internals for case 2: (a) normalized temperatures of pressurized water, reactor inlet and outlet coolant and (b) normalized temperatures of reactor internals

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