The TONUS CFD code for hydrogen risk analysis: Physical models, numerical schemes and validation matrix

被引：61

作者：

Kudriakov, S. ^{[1
]}

Dabbene, F. ^{[1
]}

Studer, E. ^{[1
]}

Beccantini, A. ^{[1
]}

Magnaud, J. P. ^{[1
]}

Paillere, H. ^{[1
]}

Bentaib, A. ^{[2
]}

Bleyer, A. ^{[2
]}

Malet, J. ^{[3
]}

Porcheron, E. ^{[3
]}

Caroli, C. ^{[2
]}

机构：

[1] CEA Saclay, DEN, DANS, DM2S,SFME,LTMF, F-91191 Gif Sur Yvette, France

[2] Inst Radioprotect & Surete Nucl, Reactor Safety Div, F-92262 Fontenay Aux Roses, France

[3] Inst Radioprotect & Surete Nucl, Plant Labs Transport & Waste Safety Div, F-91192 Gif Sur Yvette, France

来源：

NUCLEAR ENGINEERING AND DESIGN | 2008年 / 238卷 / 03期

关键词：

Risk analysis;

D O I：

10.1016/j.nucengdes.2007.02.048

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：

The French Atomic Energy Commission (CEA) and the Institute for Radiological Protection and Nuclear Safety (IRSN) are developing a hydrogen risk analysis code, called the TONUS code, which incorporates both lumped-parameter (LP) and computational fluid dynamics (CFD) formulations. In this paper we present the governing equations, numerical strategy and schemes used for the CFD approach. Several benchmark exercises based on experimental results obtained on large-scale facilities, such as MISTRA, TOSQAN and RUT, are presented. They have been used as verification and assessment procedures for modelling and numerical approaches of the code. Specific emphasis is given to the sensitivity analysis of the computed results with respect to numerical and physical parameters. The powerful Design-Of-Experiments technique for sensitivity analysis is successfully applied to the ISP47 MISTRA test case. The TONUS CFD code is presently used to support the hydrogen risk assessment for the European Pressurized Reactor (EPR) plant and to investigate the impact of the two-room concept on hydrogen distribution in the EPR containment. (c) 2007 Elsevier B.V. All rights reserved.

引用

页码：551 / 565

页数：15

共 20 条

[11]

Guermond JL, 1996, ESAIM-MATH MODEL NUM, V30, P637

[12]

HEITSCH M, 2003, REV CFD APPL CONTAIN

[13]

LETEINTURIER D, 2002, IRSNDPEADIR0201

[14]

MALET J, 2005, 11 INT TOP M NUCL RE

[15]

PAOLUCCI S, 1982, SAND858257

[16]

PORCHERON E, 2002, 10 INT S FLOW VIS KY

[17]

Spalding D.B., 1970, 13 S COMB, P649

[18] International standard problem on containment thermal-hydraulics ISP47 Step 1 - Results from the MISTRA exercise [J].

Studer, E. ;

Magnaud, J. P. ;

Dabbene, F. ;

Tkatschenko, I. .

NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (05) :536-551

[19]

STUDER E, 2003, NURETH 10

[20] A HEAT, MASS, AND MOMENTUM TRANSPORT MODEL FOR HYDROGEN DIFFUSION FLAMES IN NUCLEAR-REACTOR CONTAINMENTS [J].

TRAVIS, JR .

NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (02) :149-166

← 1 2 →