CALCULATION OF CRITICAL HEAT FLUX USING AN INVERSE HEAT TRANSFER METHOD TO SUPPORT TREAT EXPERIMENT ANALYSIS

被引：0
|
作者：
Armstrong, Robert [1 ]
Folsom, Charles [1 ]
Hill, Connie [1 ]
Jensen, Colby [1 ]
机构：
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
来源：
PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 3 | 2020年
关键词：
Transient boiling; CHF; heat transfer; TREAT;
D O I：
暂无
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：
Heat transfer between cladding and coolant during transient scenarios remains a critical area of uncertainty in understanding nuclear reactor safety. To advance the understanding of transient and accident scenarios involving critical heat flux (CHF), an in-pile experiment for the Transient Reactor Test facility (TREAT) at Idaho National Laboratory (INL) was developed. The experiment, named CHF-Static Environment Rodlet Transient Test Apparatus (CHF-SERTTA), consists of a hollow borated stainless-steel heater rod submerged in a static water pool heated via the (n, a) reaction in boron-10. This paper presents a novel inverse heat transfer method to determine CHF by using the optimization and uncertainty software Dakota to calibrate a RELAP5-3D model of CHF-SERTTA to temperature measurements obtained from a thermocouple welded to the surface of the rod.
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页数：7
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