Simulation of hydrogen distribution in an Indian Nuclear Reactor Containment

被引:52
作者
Prabhudharwadkar, Deoras M. [1 ]
Iyer, Kannan N. [1 ]
Mohan, Nalini [2 ]
Bajaj, Satinder S. [2 ]
Markandeya, Suhas G. [3 ]
机构
[1] Indian Inst Technol, Dept Mech Engn, Bombay 400076, Maharashtra, India
[2] Nucl Power Corp India Ltd, Bombay, Maharashtra, India
[3] Bhabha Atom Res Ctr, Bombay 400085, Maharashtra, India
关键词
TURBULENCE MODEL; AIR-FLOW; BEHAVIORS; TRANSPORT; PLUMES; STEAM;
D O I
10.1016/j.nucengdes.2010.11.012
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 management of hydrogen in a Nuclear Reactor Containment after LOCA (Loss Of Coolant Accident) is of practical importance to preserve the structural integrity of the containment. This paper presents the results of systematic work carried out using the commercial Computational Fluid Dynamics (CFD) software FLUENT to assess the concentration distribution of hydrogen in a typical Indian Nuclear Reactor Containment. In order to obtain an accurate estimate of hydrogen concentration distribution, a suitable model for turbulence closure is required to be selected. Using guidelines from the previous studies reported in the literature and a comparative simulation study using simple benchmark problems, the most suitable turbulence model for hydrogen mixing prediction was identified. Subsequently, unstructured meshes were generated to represent the containment of a typical Indian Nuclear Reactor. Analyses were carried out to quantify the hydrogen distribution for three cases. These were (1) Uniform injection of hydrogen for a given period of time at room temperature, (2)Time varying injection as has been computed from an accident analysis code, (3) Time varying injection (as used in case (2)) at a high temperature. A parametric exercise was also carried out in case (1) where the effect of various inlet orientations and locations on hydrogen distribution was studied. The results indicate that the process of hydrogen dispersal is buoyancy dominated. Further for typical injection rates encountered following LOCA, the dispersal is quite poor and most hydrogen is confined to the fuelling machine vault. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:832 / 842
页数:11
相关论文
共 29 条
[1]  
[Anonymous], 1954, MOL THEORY GASES LIQ, DOI DOI 10.1017/S0368393100117833
[2]  
BARTHEL V, 1991, P WORKSH HYDR BEH MI, P74
[3]   COMPARISON OF DIFFERENT K-EPSILON MODELS FOR INDOOR AIR-FLOW COMPUTATIONS [J].
CHEN, Q .
NUMERICAL HEAT TRANSFER PART B-FUNDAMENTALS, 1995, 28 (03) :353-369
[4]   Study on local hydrogen behaviors in a subcompartment of the NPP containment [J].
Choi, YS ;
Lee, UJ ;
Park, GC .
NUCLEAR ENGINEERING AND DESIGN, 2001, 208 (01) :99-116
[5]  
GANJU S, 2000, P 4 ISHMT ASME HEAT, P1271
[6]   CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment [J].
Heitsch, Matthias ;
Huhtanen, Risto ;
Techy, Zsolt ;
Fry, Chris ;
Kostka, Pal ;
Niemi, Jarto ;
Schramm, Berthold .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (02) :385-396
[7]  
IYER KN, 2005, ANAL HYDROGEN DISTRI
[8]   PREDICTION OF LAMINARIZATION WITH A 2-EQUATION MODEL OF TURBULENCE [J].
JONES, WP ;
LAUNDER, BE .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1972, 15 (02) :301-+
[9]   MULTICOMPARTMENT HYDROGEN DEFLAGRATION EXPERIMENTS AND MODEL DEVELOPMENT [J].
KANZLEITER, TF ;
FISCHER, KO .
NUCLEAR ENGINEERING AND DESIGN, 1994, 146 (1-3) :417-426
[10]   Three-dimensional behaviors of the hydrogen and steam in the APR1400 containment during a hypothetical loss of feed water accident [J].
Kim, Jongtae ;
Hong, Seong-Wan ;
Kim, Sang-Baik ;
Kim, Hee-Dong .
ANNALS OF NUCLEAR ENERGY, 2007, 34 (12) :992-1001