Preliminary steps toward assessing aerosol retention in the break stage of a dry steam generator during severe accident SGTR sequences

被引:8
|
作者
Herranz, L. E. [1 ]
del Pra, C. Lopez [1 ]
Velasco, F. J. Sanchez [1 ]
机构
[1] CIEMAT, Unit Nucl Safety Res, E-28040 Madrid, Spain
关键词
D O I
10.1016/j.nucengdes.2007.10.007
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
Severe accidents SGTR sequences are identified as major contributors to risk of PWRs. Their relevance lies in the potential radioactive release from reactor coolant system to the environment. Lack of knowledge on the source term attenuation capability of the steam generator has avoided its consideration in probabilistic safety studies and severe accident management guidelines. This paper describes a research program presently under way on the aerosol retention on the tubes surrounding the breach within the secondary side of the steam generator in the absence of water. Its development has been internationally framed within the EU-SGTR and the ARTIST program. Experimental activities are focused on setting up a reliable database in which the influence of gas mass flow rate, breach configuration and particle nature in the aerosol retention are properly considered. Theoretical activities are aimed at developing a predictive tool (ARISG) capable of assessing source term attenuation in the scenario with reasonable accuracy. Given the major importance of jet aerodynamics, 3D CFD analyses are being conducted to assist both test interpretation and model development. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:1392 / 1399
页数:8
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