Loss of primary coolant flow test is under planning by using the High Temperature engineering Test Reactor (HTTR). In this test, all the gas circulators are tripped and the position of all control rods keeps its initial one. The new calculation model was developed to perform the preliminary analysis for the test. This model is so improved that an equivalent fuel channel model based on one point kinetics code and a whole reactor model based on two-dimensional thermal analysis code are coupled to simulate the reactor performance during the loss of coolant flow. Both calculation codes were used in the safety evaluation of the HTTR licensing. The improved calculation model was validated by comparison between the calculated result and the experimental one obtained from the coolant flow reduction test in the HTTR. The loss of primary coolant flow test simulates the depressurization accident and the data obtained from the test is useful for the validation and improvement of the calculation code applied to the safety analysis in the future HTGR such as Very High Temperature Reactor which is selected as one of candidates of the generation IV reactor system.
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Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4855-5
PROCEEDINGS PAPER
The Preliminary Analysis of the Loss of Primary Coolant Flow Test in the HTTR
Shigeaki Nakagawa
,
Shigeaki Nakagawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Kuniyoshi Takamatsu
,
Kuniyoshi Takamatsu
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Minoru Goto
,
Minoru Goto
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Tetsuaki Takeda
,
Tetsuaki Takeda
University of Yamanashi, Kofu, Yamanashi, Japan
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Yasuyuki Nakao
Yasuyuki Nakao
Kyushu University, Fukuoka, Fukuoka, Japan
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Shigeaki Nakagawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Kuniyoshi Takamatsu
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Minoru Goto
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Tetsuaki Takeda
University of Yamanashi, Kofu, Yamanashi, Japan
Yasuyuki Nakao
Kyushu University, Fukuoka, Fukuoka, Japan
Paper No:
HTR2008-58282, pp. 405-412; 8 pages
Published Online:
July 1, 2009
Citation
Nakagawa, S, Takamatsu, K, Goto, M, Takeda, T, & Nakao, Y. "The Preliminary Analysis of the Loss of Primary Coolant Flow Test in the HTTR." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 405-412. ASME. https://doi.org/10.1115/HTR2008-58282
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