Modeling the partial loss of coolant flow accident in the Super-critical water reactor
Publish place: Radiation Physics and Engineering، Vol: 2، Issue: 3
Publish Year: 1400
نوع سند: مقاله ژورنالی
زبان: English
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شناسه ملی سند علمی:
JR_RPE-2-3_005
تاریخ نمایه سازی: 15 آبان 1400
Abstract:
In this study, thermal-hydraulic analysis of partial loss of coolant flow accident in supercritical pressure light water reactor (SCWR) with a new geometric design has been investigated. In the new design, the coolant and moderator circuits are separated. This analysis was performed using the development of a transient-state thermal-hydraulic code in which the equations of mass, momentum, and energy are solved. The porous Media approach is used to solve these equations. By extracting the results of transition modeling, it is observed that in the new geometric design, by separating the coolant and moderator circuits, the maximum fuel clad temperature is lower than the maximum fuel clad temperature value of the previous designs. As in the new design at the end of the transition, the maximum fuel clad temperature has decreased by about ۳۷% compared to the initial state. The result of the calculations in this study shows that the new design, in which the coolant and moderator circuits are separated, has created more safety in a chosen transition.
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Authors
Mohammad Hossein Bahrevar
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
Gholamreza Jahanfarnia
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
Ali Pazirandeh
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
Mohsen Shayesteh
Physics Department, Imam Hossein University, Tehran, Iran
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