Research on Heat Transfer Characteristics of Corium Pool Under Oscillating Conditions

被引:0
作者
Luo, Simin [1 ]
Zhan, Dekui [1 ]
Chen, Peng [1 ]
机构
[1] China Nuclear Power Technology Research Institute Co., Ltd., Guangdong, Shenzhen
来源
Hedongli Gongcheng/Nuclear Power Engineering | 2024年 / 45卷 / 05期
关键词
Corium pool; Oscillating condition; Small marine reactor;
D O I
10.13832/j.jnpe.2024.05.0128
中图分类号
学科分类号
摘要
In order to obtain the heat transfer characteristics of corium pool under oscillating conditions, an experimental study was carried out on the two-layer corium pool of small marine reactors. Fluorinert liquid FC-40 and water were used respectively to simulate the oxide layer and metal layer of corium pool in the experiment, and the transient variations of temperature field and heat transfer capacity under different oscillating conditions were obtained. The experimental results show that the oscillating conditions exert the most intense influences in the early stage of movements, and as the oscillating motion continues, the corium pool will reach a quasi-steady state of thermal equilibrium. In general, the temperature stratification of corium pool is weakened under the condition of oscillation, and the overall temperature is lower than that under the static condition, together with the increased heat transfer capacity to the cooling wall. Under the same high-intensity oscillating conditions, the effect of oscillations in vertical direction is more intense than that of oscillations in lateral direction. However, under the condition of low-intensity oscillation, the effect of oscillations in vertical direction can be ignored. Additionally, a new dimensionless parameter Lo was proposed to characterize the oscillatory influence strength, which represents the ratio of the characteristic oscillatory force to the characteristic shear force of fluid under oscillating conditions. It can be used to quantify the influence of different oscillation intensities under the same oscillation direction. This research is supposed to offer valuable reference to the in-vessel retention (IVR) analysis and safety system design for small marine reactors. © 2024 Atomic Energy Press. All rights reserved.
引用
收藏
页码:128 / 135
页数:7
相关论文
共 17 条
[1]  
ZHANG Y P, SU G H, QIU S Z, Et al., A simple novel and fast computational model for the LIVE-L4, Progress in Nuclear Energy, 68, pp. 20-30, (2013)
[2]  
KYMALAINEN O, TUOMISTO H, HONGISTO O, Et al., Heat flux distribution from a volumetrically heated pool with high Rayleigh number, Nuclear Engineering and Design, 149, 1-3, pp. 401-408, (1994)
[3]  
BONNET J M, SEILER J M., Thermal hydraulic phenomena in corium pools: the BALI experiment, 7th International Conference on Nuclear Engineering, (1999)
[4]  
Gubaidullin AA, Sehgal BR., SIMECO tests in a melt stratified pool, The 10th International Conference on Nuclear Engineering (ICONE-10), pp. 935-945, (2002)
[5]  
FLUHRER B, MIASSOEDOV A, CRON T, Et al., The LIVE-L1 and LIVE-L3 experiments on melt behaviour in RPV lower head: FZKA 7419, (2008)
[6]  
MIASSOEDOV A, CRON T, FOIT J, Et al., Results of the LIVE-L1 experiment on melt behaviour in RPV lower head performed within the LACOMERA project at the Forschungszentrum Karlsruhe, 15th International Conference on Nuclear Engineering (ICONE-15), pp. 22-26, (2007)
[7]  
GAUS-LIU X, MIASSOEDOV A, CRON T, Et al., Test and simulation results of LIVE-L4 + LIVE-L5L: KIT-SR-7593, (2011)
[8]  
ZHANG L T, ZHANG Y P, ZHOU Y K, Et al., COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers, Annals of Nuclear Energy, 87, pp. 81-88, (2016)
[9]  
ZHANG Y P, ZHANG L T, ZHOU Y K, Et al., Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers–results of COPRA experiments, Progress in Nuclear Energy, 86, pp. 80-86, (2016)
[10]  
LUO S M, ZHANG Y P, ZHOU Y K, Et al., COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt, Applied Thermal Engineering, 140, pp. 313-324, (2018)