Validation of the CFX4 CFD code for containment thermal-hydraulics

被引：53

作者：

Houkema, A. ^{[1
]}

Siccama, N. B. ^{[1
]}

Nijeholt, J. A. Lycklama a ^{[1
]}

Komen, E. M. J. ^{[1
]}

机构：

[1] Nucl Res & Consultancy Grp NRG, NL-1755 ZG Petten, Netherlands

来源：

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

关键词：

D O I：

10.1016/j.nucengdes.2007.02.033

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：

In order to determine the risk associated with the presence of hydrogen in a nuclear power plant containment during a hypothetical severe accident, thermal hydraulic codes are used. Amongst other codes, NRG uses the commercial computational fluid dynamics code CFX4 for this purpose. Models to describe condensation have been implemented by user coding. This paper describes these models. In addition, an overview is given of validation activities with the CFX4 model. Experimental results from the following sources have been used: the Kuhn condensation model; the PHEBUS test facility; the PANDA test facility; and the TOSQAN, MISTRA, and THAI test facilities within the OECD International Standard Problem 47. The CFX4 model predictions are fairly good. Deviations originate primarily from the applied wall treatment. Several recommendations for further development are therefore proposed. (c) 2007 Elsevier B.V. All rights reserved.

引用

页码：590 / 599

页数：10