Analysis of natural circulation phenomena in VVER-1000

被引:18
作者
Mousavian, SK
D'Auria, F
Salehi, MA
机构
[1] Sharif Univ Technol, Dept Mech Engn, NPP, AEOI, Tehran 9567, Iran
[2] Univ Pisa, Dipartimento Ingn Meccan & Prod, I-56126 Pisa, Italy
关键词
D O I
10.1016/j.nucengdes.2003.11.012
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
In all light water reactors (LWR), natural circulation is an important passive heat removal mechanism. In the present paper, the natural circulation phenomena are studied with reference to step-wise coolant inventory reduction and a small break loss-of-coolant-accident (SBLOCA) in the cold leg of VVER-1000. The natural circulation flow map (NCFM) approach is considered to evaluate the natural circulation performance of the VVER- 1000 NPP also comparing VVER- 1000 and PWR systems. Three different elevations between heat source (core) and heat sink (steam generators) zones have been considered in order to characterize the buoyancy force in a VVER-1000. The influence of power and the cold legs loop seal upon the natural circulation performance is also evaluated. In the second part, a series of SBLOCA simulations with break area ranging from 0.5 to 11.7% of the cold leg cross sectional area are performed starting with the VVER- 1000 system in nominal conditions. The effect of Emergency Core Cooling System (ECCS) including passive and active parts of ECCS are evaluated. The simulations were performed by the help of the system code RELAP5. Within the framework of the qualification of the adopted computational tools, the results are compared with experimental data from Kozloduy NPP unit 6 test and PSB-VVER integral test facility available from the literature. Namely, the qualification of the adopted nodalisation in steady state conditions is achieved by using experimental data. The accuracy of selected results have been estimated in quantitative terms by applying the fast Fourier transform based method (FFTBM). Finally, the relevance and the potential for the occurrence of the reflux condensation mode, i.e., one of the Natural Circulation regimes, for cooling of reactor core in VVER- 1000 are discussed. (C) 2003 Elsevier B.V. All rights reserved.
引用
收藏
页码:25 / 46
页数:22
相关论文
共 33 条
[1]  
AMBROSINI W, 1990, ENERGIA NUCL, V2, P5
[2]  
BLINKOV VN, 2003, P INT C ADV NUCL POW
[3]  
BOVALINI R, 1992, 194 DCMN NT U PIS
[4]   Code validation and uncertainties in system thermal hydraulics [J].
D'Auria, F ;
Galassi, GM .
PROGRESS IN NUCLEAR ENERGY, 1998, 33 (1-2) :175-216
[5]   Use of a natural circulation map for assessing PWR performance [J].
D'Auria, F ;
Frogheri, M .
NUCLEAR ENGINEERING AND DESIGN, 2002, 215 (1-2) :111-126
[6]   SCALING OF NATURAL CIRCULATION IN PWR SYSTEMS [J].
DAURIA, F ;
GALASSI, GM ;
VIGNI, P ;
CALASTRI, A .
NUCLEAR ENGINEERING AND DESIGN, 1991, 132 (02) :187-205
[7]  
DAURIA F, 2000, P INT C BE 2000 WASH
[8]  
DAURIA F, 1996, P 4 INT C NUCL ENG I, V3, P464
[9]  
DAURIA F, 1992, NUREGIA0084 USNRC
[10]   NATURAL CIRCULATION PHENOMENA RELEVANT TO SMALL BREAKS AND TRANSIENTS [J].
DUFFEY, RB ;
SURSOCK, JP .
NUCLEAR ENGINEERING AND DESIGN, 1987, 102 (02) :115-128