Propagation behavior of wetting front and its fluctuation characteristics during subcooled jet im**ement quenching

Y Liu, X Wu, Y Mitsutake - Advances in Mechanical …, 2024 - journals.sagepub.com
Jet im**ement quenching as one of the most effective cooling methods is widely applied
in many industrial fields. When a subcooled jet strikes the hot surface, the wetting front …

[PDF][PDF] Department of Mechanical_Engineering

KM Pandey, S Singh, P Pandey, A Sharma, U Sharma… - ijst, 2016 - nits.ac.in
37. Ajoy Debberma and KM Pandey, Numerical analysis on the effect of flow rates and jet
diameters in rewetting vertical nuclear fuel bundles with jet im**ements, Annals of Nuclear …

CFD Analysis of Rewetting Temperature and Wetting Delay during Emergency Cooling of Vertical Nuclear Fuel Rod Bundle with Water Jet Im**ement

A Debbarma, KM Pandey - Materials Today: Proceedings, 2017 - Elsevier
Numerical analysis of cooling assessment in Advance Heavy Water Reactor fuel rod bundle
with injecting water has been conducted. Two-phase simulation is modeled in CFX solver to …

CFD analysis of rewetting of a single sector AHWR fuel cluster with changing jet directions

A Debbarma, KM Pandey - Nuclear Engineering and Design, 2016 - Elsevier
The transient numerical analysis of the rewetting of Advanced Heavy Water Reactor (AHWR)
fuel assembly with jet im**ement has been conducted. The present study is concerned …

CFD Investigation on Rewetting Temperature and Wetting Delay during Quenching of Hot Surface with Jet Im**ement

DL Kishan, SL Sharma… - Advances in Mechanical …, 2022 - taylorfrancis.com
The CFD investigation has been carried out on rewetting behaviour on vertical hot surfaces
with water jet im**ement. A vertical flat plate of thickness 0.25 mm at 800° C of surface …

CFD analysis of rewetting behavior in nuclear fuel rod bundle with change in operating conditions

A Debbarma, KM Pandey - Kerntechnik, 2018 - degruyter.com
Numerical analysis on rewetting of nuclear fuel rod bundle by injecting coolant water in
radial jet direction has been performed using Computational Fluid Dynamic (CFD). CFD …

[PDF][PDF] CFD study of rewetting nuclear fuel rod bundle by zig-zag jet im**ement

A Debbarma, KM Pandey - Indian Journal of Science and …, 2016 - researchgate.net
Rewetting is the process of re-establishment of coolant contact with hot surfaces. The
present numerical analysis of rewetting nuclear fuel rod are conducted with a proposed …

[HTML][HTML] 矩形窄通道再淹没现象实验和数值研究

姬建业, 许巍, 柴翔, 刘晓晶, 曾未 - 核技术, 2017 - xml-data.org
摘要在反应堆发生大破口事故时, 再淹没阶段可以有效地降低燃料元件温度, 防止堆芯熔毁.
为了预测再淹没过程中板状燃料元件的换热特性, 进行了竖直矩形窄缝通道底部再淹没过程的 …