Loss of Coolant Accident in Pressurized Water Reactor. Prediction of a 6-inch Cold Leg Break with Relap5 and Cathare 2

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• 作者：Michał Pawluczyk ; Piotr Mazgaj ; Sebastian Gurgacz ; Michał Gatkowski ; Piotr Darnowski ; ^{michal.pawluczyk@itc.pw.edu.pl" class="auth_mail" title="E-mail the corresponding author}
• 关键词：RELAP5 ; CATHARE2 ; PWR ; IB-LOCA ; Nuclear Safety
• 刊名：Procedia Engineering
• 出版年：2016
• 出版时间：2016
• 年：2016
• 卷：157
• 期：Complete
• 页码：333-340
• 全文大小：348 K

文摘

This paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuclear Power Plant Westinghouse PWR reactor.Two thermal-hydraulic system codes were applied: RELAP5 and CATHARE 2 to simulate steady state conditions and a transient evolution. The purpose of this paper is to analyse a 6-inch cold leg break in both codes and compare calculations performed in frame of the benchmark procedure between RELAP5 and CATHARE 2 codes. Obtained steady state and transient results for both codes are comparable and predict similar accident sequences. The results are not final, and the benchmark procedure is ongoing.