Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment

被引:14
作者
Sehgal, BR [1 ]
Nourgaliev, RR [1 ]
Dinh, TN [1 ]
机构
[1] Royal Inst Technol, Div Nucl Power Safety, S-10044 Stockholm, Sweden
关键词
D O I
10.1016/S0029-5493(01)00434-4
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 results of an integral experiment on melt pool convection and vessel-creep deformation are presented and analyzed. The experiment is performed on a test facility, named Failure Of REactor VEssel Retention (FOREVER). The facility employs a 1/10-scaled 15Mo3-(German)-steel vessel of 400-mm diameter, 15-mm wall thickness and 750-mm height. A high-temperature ( similar or equal to1300 degreesC) oxide melt is prepared in a SiC-crucible placed in a 50 kW induction furnace and is. then, poured into the 1/10th scale vessel. A MoSi2 50 kW electric heater is employed in the melt pool to heat and maintain its temperature at 1200 degreesC, The vessel is pressurized with argon at the desired pressure. In the FOREVER/Cl experiment. the vessel wall, maintained at about 900 degreesC and pressurized to 26 bars. was subjected to creep deformation in a 24-h non-stop test. The FOREVER/Cl test is the first integral experiment, in which a decay-heated oxidic naturally-convecting melt pool was maintained in long-term contact with the hemispherical lower head of a pressurized. creeping. steel vessel. A sizeable database was obtained on melt pool temperatures. melt pool energy split, heat transfer rates. heat nux distribution on the melt (crust)-vessel contact surface, vessel temperatures and, in particular the vessel wall creep rate as a function of time. The paper provides information on the FOREVER/Cl measured thermal characteristics and analysis of the observed thermal behavior, The coupled nature of thermal and mechanical processes, as well as the effect of other system conditions (such as depressurization) on the melt pool and vessel temperature responses are analyzed. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:173 / 187
页数:15
相关论文
共 28 条
[1]  
ANDERSON LE, 1983, 152A EPRI IDCOR PROG
[2]  
[Anonymous], ORNLM1019
[3]  
[Anonymous], 1980, CREEP ANAL
[4]  
CHAMBERS RS, 1987, 872183 SAND
[5]   FINITE-ELEMENT ANALYSES OF A BWR VESSEL AND PENETRATION UNDER SEVERE ACCIDENT CONDITIONS [J].
CHAVEZ, SA ;
REMPE, JL .
NUCLEAR ENGINEERING AND DESIGN, 1994, 148 (2-3) :413-435
[6]  
CHU TY, 1997, 12 P NUCL THERM HYDR, P135
[7]  
DEGALTSEV Y, 1997, RPTR29 KURCH I RUSS
[8]   LOWER HEAD CREEP-RUPTURE SENSITIVITY STUDIES [J].
DOSANJH, SS ;
PILCH, M .
NUCLEAR SCIENCE AND ENGINEERING, 1991, 108 (02) :172-183
[9]   Prediction of thermoplastic failure of a reactor pressure vessel under a postulated core melt accident [J].
Duijvestijn, G ;
Birchley, J ;
Reichlin, K .
COMPUTERS & STRUCTURES, 1997, 64 (5-6) :1239-1249
[10]  
EHGAL BR, 1999, P SMIRT 15 15 INT C