In the High Temperature engineering Test Reactor (HTTR), the Vessel Cooling System (VCS) which is arranged around the reactor pressure vessel, removes residual heat and decay heat from the reactor core passively when the forced core cooling is lost. The test was carried out 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 was isolated, and three helium gas circulators in the primary cooling system were stopped to simulate the loss of forced cooling flow in the core. Moreover, one cooling line of the VCS was stopped to simulate the partial loss of cooling function from the surface of the reactor pressure vessel. The test results showed that the reactor power immediately decreased to almost zero and was stable as soon as the helium gas circulators were stopped. The power decrease is caused by negative feedback effect of reactivity. On the other hand, temperature changes of core internal structures, the reactor pressure vessel and the biological shielding concrete were slowly during the test. The measured temperature of the reactor pressure vessel decreased for several degrees during the test. The measured temperature increase of biological shielding made of concrete was small within 1 °C. The numerical analysis showed that the temperature increase of VCS cooling tube was about 15°C which is sufficiently small, which did not significantly affect the temperature of biological shielding. As the results, it was confirmed that the cooling ability of VCS can be kept sufficiently even in case that one of two water cooling lines of VCS is lost.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
PROCEEDINGS PAPER
Loss of Core Cooling Test Without One Cooling Line in Vessel Cooling System (VCS) of High Temperature Engineering Test Reactor (HTTR)
Yusuke Fujiwara,
Yusuke Fujiwara
Japan Atomic Energy Agency, Oarai, Japan
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Takahiro Nemoto,
Takahiro Nemoto
Japan Atomic Energy Agency, Oarai, Japan
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Daisuke Tochio,
Daisuke Tochio
Japan Atomic Energy Agency, Oarai, Japan
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Masanori Shinohara,
Masanori Shinohara
Japan Atomic Energy Agency, Oarai, Japan
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Masato Ono,
Masato Ono
Japan Atomic Energy Agency, Oarai, Japan
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Shimpei Hamamoto,
Shimpei Hamamoto
Japan Atomic Energy Agency, Oarai, Japan
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Kazuhiko Iigaki,
Kazuhiko Iigaki
Japan Atomic Energy Agency, Oarai, Japan
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Shoji Takada
Shoji Takada
Japan Atomic Energy Agency, Oarai, Japan
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Yusuke Fujiwara
Japan Atomic Energy Agency, Oarai, Japan
Takahiro Nemoto
Japan Atomic Energy Agency, Oarai, Japan
Daisuke Tochio
Japan Atomic Energy Agency, Oarai, Japan
Masanori Shinohara
Japan Atomic Energy Agency, Oarai, Japan
Masato Ono
Japan Atomic Energy Agency, Oarai, Japan
Shimpei Hamamoto
Japan Atomic Energy Agency, Oarai, Japan
Kazuhiko Iigaki
Japan Atomic Energy Agency, Oarai, Japan
Shoji Takada
Japan Atomic Energy Agency, Oarai, Japan
Paper No:
ICONE24-60858, V002T06A035; 7 pages
Published Online:
October 25, 2016
Citation
Fujiwara, Y, Nemoto, T, Tochio, D, Shinohara, M, Ono, M, Hamamoto, S, Iigaki, K, & Takada, S. "Loss of Core Cooling Test Without One Cooling Line in Vessel Cooling System (VCS) of High Temperature Engineering Test Reactor (HTTR)." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T06A035. ASME. https://doi.org/10.1115/ICONE24-60858
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