Thermal-hydraulics analysis during fuel element failure in an operating PWR |
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| Affiliation: | 1. Department of Nuclear Energy Science and Engineering, Naval University of Engineering, Wuhan 430033, China;2. Institute of Thermal Science and Power Engineering, Naval University of Engineering, Wuhan 430033, China;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;1. Department of Nuclear Engineering, Pakistan Institute of Engineering and Applied Sciences (PIEAS), P. O. Nilore, 45650, Islamabad, Pakistan;2. Department of Physics, COMSTATS Institute of Information Technology, Islamabad, Pakistan;1. Department of Energy Engineering, Sharif University of Technology, Tehran 8639-11365, Iran;2. Advanced Nuclear Computational Center, Tehran 8741-21672, Iran;1. Department of Physics, Air University, PAF Complex, E-9, Islamabad 44000, Pakistan;2. Department of Nuclear Engineering, Pakistan Institute of Engineering & Applied Sciences (PIEAS), Post Office Nilore, Islamabad 45650, Pakistan;3. Department of Physics & Applied Mathematics, Pakistan Institute of Engineering & Applied Sciences (PIEAS), Post Office Nilore, Islamabad 45650, Pakistan |
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| Abstract: | The fuel element failure in an operating pressurized water reactor (PWR), including fuel element breaks, has an effect on the operation safety of PWR. In this paper, the RELAP5 model of the fuel element failure is established for the safety analysis. The RELAP5 time step sensitivity analyses for the element pre-break steady and post-break transient simulation are carried out. And the variations of main thermal-hydraulics parameters related to the fuel element break are quantitatively studied, which include the internal gap pressure and the maximum fuel pellet temperature as well as the releasement of noncondensables in the gap. It is found that (1) the results by the RELAP5 code is very sensitive to the time step in a volume system with the noncondensables, and the time step sensitivity analysis is necessary if the effective time step range is unknown, (2) the larger the break area is, the more quickly the gap pressure increases and the maximum pellet temperature reaches to the stable value, (3) when the gap pressure increases and reaches to the coolant pressure, at the break the liquid inflow from coolant to gap will be turned to the vapor outflow from gap to coolant, (4) during the failure transient, the gap thermal conductivity experiences a sharp decrease in the break instant, which results in the decrease of heat transferred to cladding and the sharp decrease of cladding temperature as well as the sharp increase of minimum departure from nucleate boiling ratio (MDNBR). These conclusions can provide the basic for the operation safety analysis of PWR during the fuel element failure. |
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| Keywords: | PWR Fuel element failure RELAP5 Safety analysis |
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