Modelling of two-phase flow under accidental conditions fusion codes benchmark

被引：11
|
作者：
Sardain, P
Girard, C
Andersson, J
Porfiri, MT
Kurihara, R
Masson, X
Mignot, G
Pinna, T
Topilski, L
机构：
[1] CEA Cadarache, SERSI, DER, F-13108 St Paul Durance, France
[2] ENEA, Frascati, Italy
[3] JAERI, Naka, Ibaraki, Japan
[4] ITER JCT, Garching, Germany
来源：
FUSION ENGINEERING AND DESIGN | 2001年 / 54卷 / 3-4期
关键词：
Thermal hydraulic codes;
D O I：
10.1016/S0920-3796(00)00584-6
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 scope of this benchmark is to assess the capabilities of the best estimate thermal hydraulic codes to simulate the main physical phenomena occurring during an in-vessel break transient within a water-cooled fusion-type reactor: pressurisation of a volume at low initial pressure, critical flow, counter pressure effect, relief into an expansion volume. The results, which are given by the code are of the same order of magnitude. Discrepancies are observed which are mainly due to the different ways the codes simulate the break mass flow rate and the pressurisation of the vacuum vessel. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：555 / 561
页数：7
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