Primary loop analysis for a PWR contains Passive Core Cooling System; LOCA and clad rising temperature
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- 作者：M.H. Porhemmata ; F. Faghihia ; b ; c ; faghihif@shirazu.ac.ir" class="auth_mail" title="E-mail the corresponding author ; A. Rabieea
- 关键词：Reduced Primary Model (RPM) ; AP1000 ; LOCA ; Passive Core Cooling System (PCCS) ; Clad temperature ; RELAP5
- 刊名：Annals of Nuclear Energy
- 出版年：2016
- 出版时间：May 2016
- 年：2016
- 卷：91
- 期：Complete
- 页码：8-21
- 全文大小：1127 K
文摘
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A reduced order primary model (RPM) is examined for the primary loop of a modern PWR which includes passive safety guards.
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Fundamental neutronics and thermal–hydraulics equations for the primary loop of a modern PWR are investigated based on RPM.
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Two break size of LOCA is modelled using RPM, and results are benchmarked by RELAP5/mode 3 code.
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Loss of primary pumps and diesel generators due to Tsunami scenario are supposed.
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Based on RPM and described design basis accident scenario, clad rising temperature are investigated.