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

共 50 条

[31] VERIFICATION OF RELAP5/mod3.2 CRITICAL HEAT TRANSFER COMPUTATIONAL METHOD BY EXPERIMENTS PERFORMED ON THE KS FACILITY
Afremov, D. A.
Yashnikov, D. A.
ATOMIC ENERGY, 2011, 110 (05) : 328 - 331
[32] Development and Verification of Thermal-hydraulic System Analysis Code Based on RELAP5 MOD3.2 for SFRs
Song J.
Tan C.
Tang S.-M.
Liu L.-M.
Tian W.-X.
Wu Y.-W.
Qiu S.-Z.
Su G.-H.
1600, Atomic Energy Press (51): : 994 - 1001
[33] Improvement of Relap5/Mod3.2 based on high-pressure horizontal- stratified TPTF experiment
He, Shuang-Ji
Xie, Heng
Hedongli Gongcheng/Nuclear Power Engineering, 2012, 33 (05): : 41 - 44
[34] RELAP5/MOD2 ANALYSIS OF N REACTOR COLD-LEG MANIFOLD BREAK TRANSIENT WITHOUT SCRAM
SATHYANARAYANA, K
OGDEN, DM
NUCLEAR TECHNOLOGY, 1990, 92 (02) : 194 - 203
[35] Analysis of metastable regimes in a parallel channel single phase natural circulation system with RELAP5/MOD3.2
Gartia, M. R.
Pilkhwal, D. S.
Vijayan, P. K.
Saha, D.
INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2007, 46 (10) : 1064 - 1074
[36] Verification of relap5/mod3.2 critical heat transfer computational method by experiments performed on the ks facility
D. A. Afremov
D. A. Yashnikov
Atomic Energy, 2011, 110 : 328 - 331
[37] Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
Hedayat, A.
KERNTECHNIK, 2019, 84 (01) : 29 - 47
[38] Direct-contact condensation heat transfer model in RELAP5/MOD3.2 with/without noncondensable gases for horizontally stratified flow
Choi, KY
Chung, HJ
No, HC
NUCLEAR ENGINEERING AND DESIGN, 2002, 211 (2-3) : 139 - 151
[39] Validation of heat transfer models in narrow gap for RELAP/SCDAPSIM/MOD3.2
Kohriyama, T
Murase, M
Nagae, T
Okano, Y
Ezzidi, A
NUCLEAR TECHNOLOGY, 2004, 147 (02) : 191 - 201
[40] IMPLEMENTATION OF LIQUID METAL PROPERTIES IN RELAP5 MOD3.2 FOR SAFETY ANALYSIS OF SODIUM-COOLED FAST REACTORS
Song, Jian
Liu, Limin
Tang, Simiao
Wu, Yingwei
Tian, Wenxi
Qiu, Suizheng
Su, Guanghui
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 9, 2017,

← 1 2 3 4 5 →