Reflood Investigation of Model Fuel Assemblies of Light-Water Reactors for a Loss-of-Coolant Accident

被引:1
作者
Bazyuk, S. S. [1 ,2 ]
Parshin, N. Ya. [1 ,2 ]
Popov, E. B. [1 ,2 ]
Kuzma-Kichta, Yu. A. [3 ]
机构
[1] Luch Res Inst, Podolsk, Moscow Oblast, Russia
[2] Sci Ind Assoc NII NPO Luch, Podolsk, Moscow Oblast, Russia
[3] Natl Res Univ, Moscow Power Engn Inst MEI, Moscow, Russia
基金
俄罗斯基础研究基金会;
关键词
Fuels - Loss of coolant accidents - Pressurized water reactors - Heat flux;
D O I
10.1007/s10512-014-9863-7
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 a reflood investigation of model VVER and PWR fuel assemblies for maximum design-basis and beyond design-basis accidents performed on the RBHT, SVD, and PARAMETR stands are presented. The variation ranges of the regime parameters are: initial temperature of fuel element 460-600A degrees C; mass velocity of water 47-160 kg/(m(2)center dot sec), underheating at the entry into the model fuel assembly 11-108A degrees C; pressure 0.14-0.42 MPa; and, linear heat flux density simulating the residual heat release 0-2.3 kW/m. A colligating relation describing the experimental data to within 30% is obtained for the wetting front of model fuel assemblies, which makes it possible to calculate the cool-down time of model fuel assemblies with different designs and evaluate the reflooding time of VVER and PWR.
引用
收藏
页码:343 / 349
页数:7
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