Validation of RELAP5/MOD3.2 model of VVER440 on reactor scram transient

被引：6

作者：

Groudev, P ^{[1
]}

Stefanova, A ^{[1
]}

机构：

[1] Bulgarian Acad Sci, Inst Nucl Res & Nucl Energy, BU-1784 Sofia, Bulgaria

来源：

PROGRESS IN NUCLEAR ENERGY | 2006年 / 48卷 / 02期

关键词：

VVER; NPP; thermal hydraulic code; experimental data; validation; RELAP5;

D O I：

10.1016/j.pnucene.2005.08.001

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

This paper describes validation of a computer model that has been developed for VVER 440 Nuclear Power Plant (NPP) for use with RELAP5/M0D 3.2 computer code in the analysis of the following transient: 'Reactor SCRAM'. This validation is a process that compares the analytical results obtained by RELAP5/MOD3.2 model of the VVER 440 with the experimental transient data received from Kozloduy NPP, Unit #2. The model of VVER 440 was developed at the Institute for Nuclear Research and Nuclear Energy for analyses of operational occurrences, abnormal events, and design basis scenarios. It will provide a significant analytical capability for the Bulgarian technical specialists located at the Kozloduy NPP. The criteria used in selecting transient are: importance to safety, availability and suitability of data followed by suitability for RELAP5 code validation. The comparisons between the RELAP5 results and the test data indicate good agreement. (c) 2005 Elsevier Ltd. All rights reserved.

引用

页码：146 / 154

页数：9