Numerical investigation of thermal hydraulic behaviors in wire-wrapped bundle with smaller wire diameter of peripheral rods

Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle

(2021) Mason Childs et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

CFD investigation for a 7-pin wire-wrapped fuel assembly with different shapes of fuel duct wall

(2020) Yuanyuan Zhao et al.   ANNALS OF NUCLEAR ENERGY

An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle

(2020) Yu Liang et al.   APPLIED THERMAL ENGINEERING

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

NACIE-UP post-test simulations by CFD codes

(2019) A. Pucciarelli et al.   NUCLEAR ENGINEERING AND DESIGN

Stereoscopic PIV measurements of near-wall flow in a tightly packed rod bundle with wire spacers

(2018) Thien Nguyen et al.   EXPERIMENTAL THERMAL AND FLUID SCIENCE

Thermal-hydraulic effects of inserts in a fast reactor fuel bundle

(2018) G. Padmakumar et al.   NUCLEAR ENGINEERING AND DESIGN

The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles

(2018) S.K. Chen et al.   NUCLEAR ENGINEERING AND DESIGN

High fidelity numerical simulations of an infinite wire-wrapped fuel assembly

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

Thermal-hydraulic effect of wire spacer in a wire-wrapped fuel bundles for SFR

(2017) Jae-Ho Jeong et al.   NUCLEAR ENGINEERING AND DESIGN

Thermal-hydraulic study of the LBE-cooled fuel assembly in the MYRRHA reactor: Experiments and simulations

(2017) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

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

CFD investigation of effect of helical wire-wrap parameters on the thermal hydraulic performance of 217 fuel pin bundle

(2015) R. Gajapathy et al.   ANNALS OF NUCLEAR ENERGY

A quantitative CFD benchmark for Sodium Fast Reactor fuel assembly modeling

(2013) J.W. Fricano et al.   ANNALS OF NUCLEAR ENERGY

Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles

(2013) S.K. Chen et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical simulation of the flow in wire-wrapped pin bundles: Effect of pin-wire contact modeling

(2011) E. Merzari et al.   NUCLEAR ENGINEERING AND DESIGN