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

Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System

(2020) Dekui Zhan et al.   Science and Technology of Nuclear Installations

Flow boiling CHF enhancement by wettability and flow conditions in a slug flow in the rectangular curved channel

(2018) Hae Min Park et al.   EXPERIMENTAL THERMAL AND FLUID SCIENCE

Effects of surface orientation and heater material on heat transfer coefficient and critical heat flux of nucleate boiling

(2018) Yong Mei et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

A margin missed: The effect of surface oxidation on CHF enhancement in IVR accident scenarios

(2018) Mathias Trojer et al.   NUCLEAR ENGINEERING AND DESIGN

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

In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues

(2017) J. L. Rempe et al.   NUCLEAR TECHNOLOGY

Nanofluids for Enhanced Economics and Safety of Nuclear Reactors: An Evaluation of the Potential Features, Issues, and Research Gaps

(2017) Jacopo Buongiorno et al.   NUCLEAR TECHNOLOGY

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

Study on structural failure of RPV with geometric discontinuity under severe accident

(2016) J.F. Mao et al.   NUCLEAR ENGINEERING AND DESIGN

A new method to study the transient feasibility of IVR-ERVC strategy

(2016) Rui Guo et al.   PROGRESS IN NUCLEAR ENERGY

In-vessel retention coolability evaluation for Chinese improved 1000 MWe PWR

(2015) Y.B. Li et al.   ANNALS OF NUCLEAR ENERGY

Effects of turbulence models on forced convection subcooled boiling in vertical pipe

(2015) Rui Zhang et al.   ANNALS OF NUCLEAR ENERGY

In- and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR

(2015) Yue Jin et al.   ANNALS OF NUCLEAR ENERGY

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

(2015) P. Tusheva et al.   ANNALS OF NUCLEAR ENERGY

Prediction of CHF in vertical heated tubes based on CFD methodology

(2015) Rui Zhang et al.   PROGRESS IN NUCLEAR ENERGY

CFD analysis on subcooled boiling phenomena in PWR coolant channel

(2015) Rui Zhang et al.   PROGRESS IN NUCLEAR ENERGY

A theoretical CHF model for subcooled flow boiling in curved a channel at low pressure

(2014) R. Guo et al.   ANNALS OF NUCLEAR ENERGY

Effect of heater material and coolant additives on CHF for a downward facing curved surface

(2014) Hae Min Park et al.   NUCLEAR ENGINEERING AND DESIGN

Can corrosion and CRUD actually improve safety margins in LWRs?

(2013) Jacopo Buongiorno   ANNALS OF NUCLEAR ENERGY

Feasibility of flooding the reactor cavity with liquid gallium coolant for IVR-ERVC strategy

(2013) Seong Dae Park et al.   NUCLEAR ENGINEERING AND DESIGN

Critical heat flux for APR1400 lower head vessel during a severe accident

(2013) Sang W. Noh et al.   NUCLEAR ENGINEERING AND DESIGN

Flow boiling CHF enhancement in an external reactor vessel cooling (ERVC) channel using graphene oxide nanofluid

(2013) Seong Dae Park et al.   NUCLEAR ENGINEERING AND DESIGN

The effect of the geometric scale on the critical heat flux for the top of the reactor vessel lower head

(2013) Hae Min Park et al.   NUCLEAR ENGINEERING AND DESIGN

EXPERIMENTAL STUDY OF CRITICAL HEAT FLUX WITH ALUMINA-WATER NANOFLUIDS IN DOWNWARD-FACING CHANNELS FOR IN-VESSEL RETENTION APPLICATIONS

(2013) G. DEWITT et al.   Nuclear Engineering and Technology

An experimental study on CHF in pool boiling system with SA508 test heater under atmospheric pressure

(2012) Juno Lee et al.   NUCLEAR ENGINEERING AND DESIGN

CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy

(2011) Tae Il Kim et al.   NUCLEAR ENGINEERING AND DESIGN

AN AXIOMATIC DESIGN APPROACH OF NANOFLUID-ENGINEERED NUCLEAR SAFETY FEATURES FOR GENERATION III+ REACTORS

(2011) In-Cheol Bang et al.   Nuclear Engineering and Technology

NANOTECHNOLOGY FOR ADVANCED NUCLEAR THERMAL-HYDRAULICS AND SAFETY: BOILING AND CONDENSATION

(2011) In-Cheol Bang et al.   Nuclear Engineering and Technology

Design process of the nanofluid injection mechanism in nuclear power plants

(2011) Myoung-suk Kang et al.   Nanoscale Research Letters

CHF enhancement in flow boiling system with TSP and boric acid solutions under atmospheric pressure

(2010) Juno Lee 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

Review of convective heat transfer enhancement with nanofluids

(2009) Sadik Kakaç et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

A feasibility assessment of the use of nanofluids to enhance the in-vessel retention capability in light-water reactors

(2008) J. Buongiorno et al.   NUCLEAR ENGINEERING AND DESIGN

Fracture mechanical evaluation of an in-vessel melt retention scenario

(2007) M. Abendroth et al.   ANNALS OF NUCLEAR ENERGY

Flow boiling CHF enhancement with surfactant solutions under atmospheric pressure

(2007) Yong Hoon Jeong et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER