Experimental study on the adsorption and desorption of tritium in the graphite materials for HTR-PM |
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| Affiliation: | 1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;2. Collaborative Innovation Center of Advanced Nuclear Energy Technology, Beijing 100084, China;3. The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing, 100084, China;1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin, Heilongjiang, 150001, China;2. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610041, China;3. School of Energy and Power Engineering, Northeast Dianli University, Jilin, 132012, China;4. State Key Laboratory of Hydraulics and Mountain River Engineering, College of Water Resource & Hydropower, Sichuan University, Chengdu, 610065, China;1. Centre de recherche nucléaire de birine, BP 180, Djelfa 17200, Algeria;2. Facoltà di Ingegneria, Università di Pisa, Via Diotisalvi, 2, Pisa, Italy;3. University of El-Oued, 39000, Algeria;4. Université Ferhat Abbas de Setif, Algeria;1. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1, Ookayama, Meguro-ku, Tokyo 152-8550, Japan;2. Advanced Science Research Center, Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195, Japan;1. Department of Nuclear Science and Technology, Xi''an Jiaotong University, Xi''an City 710049, China;2. Key Laboratory Advanced Reactor Engineering and Safety, Ministry of Education of China, China |
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| Abstract: | Tritium behavior in the reactor such as production, diffusion and release are accompanied by their adsorption and desorption in graphite materials, which are essential to the safety of high temperature gas cooled reactor (HTGR). In order to study this important issue, hydrogen instead of tritium is experimentally used in this work and justified viable by theory. By performing multiple sets of comparative experiments, the features of hydrogen adsorption and desorption behavior changing by adsorption temperature and time in typical graphites used in HTR-PM (High Temperature Gas Cooled Reactor – Pebble Bed Module), i.e. reflective layer, fuel element and boron carbon bricks, have been observed and analyzed. Furthermore, the adsorption rates of hydrogen in the three materials as above at different conditions are also given. Based on the experimental results, tritium behavior in the HTR-PM was inferred and estimated, which is significant for the further study on the mechanism of tritium transport. |
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| Keywords: | Tritium Graphite HTR-PM Adsorption Desorption |
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