Sub-channel code development of lead-bismuth eutectic fast reactor available for multiple fuel assembly structures

Experimental tests and post-test analysis of non-uniformly heated 19-pins fuel bundle cooled by Heavy Liquid Metal

(2019) R. Marinari et al.   NUCLEAR ENGINEERING AND DESIGN

Experimental study of the influence of inter-wrapper flow on liquid-metal cooled fuel assemblies

(2019) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes

(2018) Shiying Wei et al.   NUCLEAR ENGINEERING AND DESIGN

A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions

(2018) A. Moorthi et al.   NUCLEAR ENGINEERING AND DESIGN

Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE

(2018) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

Transient sub-channel code development for lead-cooled fast reactor using the second-order upwind scheme

(2018) Liankai Cao et al.   PROGRESS IN NUCLEAR ENERGY

Experimental study on thermal-hydraulic behaviour of LBE and water interface

(2017) Wangli Huang et al.   PROGRESS IN NUCLEAR ENERGY

Experimental investigation of a LBE-helium heat exchanger based the ADS

(2017) Yongwei Wang et al.   PROGRESS IN NUCLEAR ENERGY

Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic

(2016) Kefeng Lyu et al.   ANNALS OF NUCLEAR ENERGY

Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers

(2016) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility

(2016) Ivan Di Piazza et al.   NUCLEAR ENGINEERING AND DESIGN

Development of a sub-channel code for liquid metal cooled fuel assembly

(2015) X.J. Liu et al.   ANNALS OF NUCLEAR ENERGY

Heat transfer to liquid metals in a hexagonal rod bundle with grid spacers: Experimental and simulation results

(2015) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

HLM fuel pin bundle experiments in the CIRCE pool facility

(2015) Daniele Martelli et al.   NUCLEAR ENGINEERING AND DESIGN

Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers

(2014) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

Experimental and numerical study on lead–bismuth heat transfer in a fuel rod simulator

(2011) Weimin Ma et al.   JOURNAL OF NUCLEAR MATERIALS

TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods

(2010) Aaron Epiney et al.   ANNALS OF NUCLEAR ENERGY

Analytical prediction of turbulent friction factor for a rod bundle

(2010) Jun Ho Bae et al.   ANNALS OF NUCLEAR ENERGY

Thermal-hydraulic performance of heavy liquid metal in straight-tube and U-tube heat exchangers

(2009) Weimin Ma et al.   NUCLEAR ENGINEERING AND DESIGN

Heat transfer to liquid metal: Review of data and correlations for tube bundles

(2009) Konstantin Mikityuk   NUCLEAR ENGINEERING AND DESIGN

Thermodynamic properties and equation of state of liquid lead and lead–bismuth eutectic

(2008) V.P. Sobolev et al.   JOURNAL OF NUCLEAR MATERIALS