| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 5030343 | Procedia Engineering | 2016 | 8 Pages |
Abstract
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.
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Physical Sciences and Engineering
Engineering
Engineering (General)
Authors
MichaÅ Pawluczyk, Piotr Mazgaj, Sebastian Gurgacz, MichaÅ Gatkowski, Piotr Darnowski,