Sensitivity study on in-box LOCA for a Korean HCCR TBM in ITER |
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| Affiliation: | 1. Korea Atomic Research Institute, Daejeon, Republic of Korea;2. National Fusion Research Institute, Daejeon, Republic of Korea;1. Nuclear Engineering and Technology Programme, Indian Institute of Technology, Kanpur 208016, India;2. Innovative Systems Software, Idaho Falls, ID 83406, USA;1. Graduate School of Engineering Technology, Lunghwa University of Sci. & Tech., No.300, Sec.1, Wanshou Rd., Guishan Shiang, Taoyuan County 33306, Taiwan, ROC;2. Industrial Technology Research Institute, Material and Chemical Research Laboratories, RM 824, Bldg.52, No.195, Sec.4, Chung Hsing Rd., Chutung, Hsinchu 31040, Taiwan, ROC;3. National Chung Hsing University, Department of Applied Mathematics, 250 Kuo Kuang Rd., Taichung 402, Taiwan, ROC;4. Department of Nuclear Safety, Taiwan Power Company, No.242, Sec. 3, Roosevelt Rd., Zhongzheng District, Taipei City 100, Taiwan, ROC;1. Department of Civil and Environmental Engineering, Politecnico di Milano, Milan, Italy;2. Department of Structural Geotechnical and Building Engineering, Politecnico di Torino, Turin, Italy;1. Nuclear and Radiation Safety Center, P. O. Box 8088, Beijing, China;2. ITER Organization, Route de Vinon-sur-Verdon, 13115 Saint-Paul-lès-Durance, France;3. China Institute of Atomic Energy, P. O. Box 275(34), Beijing, China |
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| Abstract: | Korea has designed a Helium-Cooled Ceramic Reflector (HCCR)-based Test Blanket System (TBS) for International Thermonuclear Experimental Reactor (ITER). Among seven selected reference accidents in Korean TBS, in-box loss of coolant accident (LOCA) is one of them. This is initiated by a double-ended break of the coolant pipe in the Breeding Zone (BZ), pressurizing the BZ box structure, causing pressurization of the Tritium Extraction System (TES) and purging of pipelines. When the accident is detected, the Plant Safety System (PSS) isolates the Helium Cooling System (HCS) and TES, and requests plasma shutdown to Fusion Power Shutdown System (FPSS). To prevent aggravating failure of the system, the safety function is automatically activated when the accident is detected, the device being the isolation valve of HCS and TES. One important observation of this accident is that instant isolation is not a good measure to take. In terms of the possibility of aggravating failure, system isolation is an important safety procedure but isolated TES volume is exposed to high pressure and temperature conditions in the early move of the accident transient. The result of system safety analysis shows that delayed isolation keeps the system safe for a while. In this article, given the preliminary accident analysis results for the current HCCR TBS, case studies were performed regarding the delayed isolation timing effect. For this transient simulation, Korean nuclear fusion reactor safety analysis code (GAMMA-FR) was used. |
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| Keywords: | in-box LOCA TBS ITER Safety analysis Scoping study |
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