Numerical analysis of debris melting phenomena during late phase CANDU 6 severe accident

被引:17
作者
Nicolici, Stefan [1 ]
Dupleac, Daniel [1 ]
Prisecaru, Ilie [1 ]
机构
[1] Univ Politehn Bucuresti, Power Plant Engn Fac, RO-060042 Bucharest, Romania
关键词
HEATED LIQUID POOLS; SIMULATION;
D O I
10.1016/j.nucengdes.2012.09.023
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 objective of this paper was to study the phase change of the debris formed on the CANDU 6 calandria bottom in a postulated accident sequence. The molten pool and crust formation were studied employing the Ansys Fluent code. Two models using Large Eddy Simulation and Phase Change Effective Convectivity Model (PECM) predict the conjugate, radiative and convective heat transfer inside and from the corium pool. LES require a very fine grid to capture the crust formation and the free convection flow. This aspect (fine mesh requirement) correlated with the long transient has imposed the use of a slice from the 3D calandria geometry in order not to exceed the computing resources. From the safety point of view it is very important to maintain a heat flux through the wall below the critical heat flux assuring the integrity of the calandria vessel, thus the paper results include temperature profiles and heat fluxes through calandria wall. The results predicted by the PECM approach are comparable within 10% with those obtained by the computational fluid dynamics method, proving that the PECM can be used to perform further sensitivity studies. (c) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码:272 / 279
页数:8
相关论文
共 21 条
[1]   Role of RELAP/SCDAPSIM in Nuclear Safety [J].
Allison, C. M. ;
Hohorst, J. K. .
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2010, 2010
[2]  
[Anonymous], 2008, SEVERE CORE DAMAGE A
[3]  
Ansys Inc, 2009, US MAN ANSYS FLUENT
[4]   BUOYANT TURBULENT-FLOW DRIVEN BY INTERNAL ENERGY GENERATION [J].
ARPACI, VS .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1995, 38 (15) :2761-2770
[5]  
Baehr H.D., 2008, FUNDAMENTALS MOMENTU, Vsecond
[6]  
Bui V. A., 1996, P 2 EUR THERM SCI C, P1365
[7]  
Cheung F. B., 1992, 28 NAT HEAT TRANSF C
[8]   Turbulence modelling for large volumetrically heated liquid pools [J].
Dinh, TN ;
Nourgaliev, RR .
NUCLEAR ENGINEERING AND DESIGN, 1997, 169 (1-3) :131-150
[9]   Generic CANDU 6 plant severe accident analysis employing SCAPSIM/RELAP5 code [J].
Dupleac, Daniel ;
Mladin, Mirea ;
Prisecaru, Ilie .
NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (10) :2093-2103
[10]  
International atomic energy agency, 2008, IAEA-TECDOC-1594