Numerical study of thermal-hydraulic and structural parameters effects on CHF in subcooled forced convection flow during external reactor vessel cooling

A review on the external cooling of the pressure vessel lower head in nuclear power plant

(2023) Yandong Hou et al.   NUCLEAR ENGINEERING AND DESIGN

Flow boiling experiments for CHF evaluation under downward-facing heating including flow visualization: Effects of pressure, orientation, mass flux, and local quality

(2022) Jun Yeong Jung et al.   ANNALS OF NUCLEAR ENERGY

Heat transfer experiment with the prototypical Ra number of heavy metallic layer in IVR strategy

(2022) Zongyang Li et al.   PROGRESS IN NUCLEAR ENERGY

Numerical study on the effects of guide thimble on critical heat flux in a 5 × 5 fuel assembly

(2022) Tenglong Cong et al.   ANNALS OF NUCLEAR ENERGY

Studies on the critical heat flux in fuel assembly using a modified two-phase multi-scale interface model—validation and sensitivity analysis

(2021) Xiang Zhang et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces

(2020) Irfan Khan et al.   PROGRESS IN NUCLEAR ENERGY

Recent progress of CFD applications in PWR thermal hydraulics study and future directions

(2020) Mingjun Wang et al.   ANNALS OF NUCLEAR ENERGY

Analysis on CHF deviation caused by geometry of the heater blocks in a validation test of IVR-ERVC technology

(2020) Daogang Lu et al.   ANNALS OF NUCLEAR ENERGY

CAP1400 IVR related design features and assessment

(2019) Guobao Shi et al.   NUCLEAR ENGINEERING AND DESIGN

Influences of some engineered factors on IVR-ERVC limits

(2019) Bo Kuang et al.   NUCLEAR ENGINEERING AND DESIGN

An experimental study on natural circulation flow characteristics under passive IVR-ERVC conditions

(2019) Fan Wang et al.   ANNALS OF NUCLEAR ENERGY

A theoretical and experimental study on subcooled flow boiling under passive IVR-ERVC conditions

(2019) Fan Wang et al.   ANNALS OF NUCLEAR ENERGY

Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools

(2018) Luteng Zhang et al.   ANNALS OF NUCLEAR ENERGY

CHF correlation development under ERVC conditions by using the local liquid velocity from PIV measurements

(2018) Jongwoong Yoon et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Numerical prediction of CHF based on CFD methodology under atmospheric pressure and low flow rate

(2018) Yapei Zhang et al.   APPLIED THERMAL ENGINEERING

Experimental study on CHF using a full scale 2-D curved test section with additives and SA508 heater for IVR-ERVC strategy

(2017) Huajian Chang et al.   EXPERIMENTAL THERMAL AND FLUID SCIENCE

Experimental investigation of 3-D ERVC process for IVR strategy – CHF limits and visualization of boiling phenomena

(2017) Wei Lu et al.   NUCLEAR ENGINEERING AND DESIGN

The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head

(2016) Y.P. Zhang et al.   ANNALS OF NUCLEAR ENERGY

CFD simulation on critical heat flux of flow boiling in IVR-ERVC of a nuclear reactor

(2016) Xiang Zhang et al.   NUCLEAR ENGINEERING AND DESIGN

Validation of NEPTUNE_CFD on ULPU-V experiments

(2015) Mathieu Jamet et al.   NUCLEAR ENGINEERING AND DESIGN

Analysis of safety margin of in-vessel retention for AP1000

(2010) Y.P. Zhang et al.   NUCLEAR ENGINEERING AND DESIGN

In-vessel melt pool coolibility test—Description and results of LIVE experiments

(2010) X. Gaus-Liu et al.   NUCLEAR ENGINEERING AND DESIGN