Thermal‐hydraulic analysis of wire‐wrapped rod bundle in lead‐based fast reactor with non‐uniform heat flux

Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor

(2022) Xiao Luo et al.   Nuclear Science and Techniques

Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

(2021) Rui Yu et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

RANS simulations for transition and turbulent flow regimes in wire-wrapped rod bundles

(2021) Octavio Bovati et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

CFD investigation for a 7-pin wrapped-wire fuel assembly with different wires

(2021) Junjie Lin et al.   ANNALS OF NUCLEAR ENERGY

Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles

(2021) Octavio Bovati et al.   ANNALS OF NUCLEAR ENERGY

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

(2021) Kefeng Lyu et al.   ANNALS OF NUCLEAR ENERGY

Flow blockage analysis for fuel assembly in a lead-based fast reactor

(2021) Chenglong Wang et al.   Nuclear Engineering and Technology

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

Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes

(2020) Yan Zhang et al.   APPLIED THERMAL ENGINEERING

Experimental investigation of turbulent wake flows in a helically wrapped rod bundle in presence of localized blockages

(2020) T. Nguyen et al.   PHYSICS OF FLUIDS

Thermal-hydraulic analysis of a 7-pin sodium-cooled fast reactor wire-wrapped fuel bundle

(2020) Dianle Wang et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle

(2019) Xiang Chai et al.   NUCLEAR ENGINEERING AND DESIGN

PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly

(2019) Cheng Zhang et al.   Nuclear Engineering and Technology

Computational fluid dynamics and subchannel analysis of lead–bismuth eutectic-cooled fuel assembly under various blockage conditions

(2019) X.J. Liu et al.   APPLIED THERMAL ENGINEERING

Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors

(2019) Yan Zhang et al.   RENEWABLE & SUSTAINABLE ENERGY REVIEWS

CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor

(2018) Jing Chen et al.   ANNALS OF NUCLEAR ENERGY

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

Core design of long‐cycle small modular lead‐cooled fast reactor

(2018) Tung Dong Cao Nguyen et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

Thermal-hydraulic comparisons of 19-pin rod bundles with four circular and trapezoid shaped wire wraps

(2017) Li Liu 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

Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactor

(2016) M. Naveen Raj et al.   ANNALS OF 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

Development strategy and conceptual design of China Lead-based Research Reactor

(2016) Yican Wu et al.   ANNALS OF NUCLEAR ENERGY

Thermal–hydraulic performance of a 5 × 5 rod bundle with spacer grid in a nuclear reactor

(2016) Deqi Chen et al.   APPLIED THERMAL ENGINEERING

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

Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly

(2016) E. Merzari 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

The core design of ALFRED, a demonstrator for the European lead-cooled reactors

(2014) G. Grasso et al.   NUCLEAR ENGINEERING AND DESIGN

Generation IV International Forum: A decade of progress through international cooperation

(2014) John E. Kelly   PROGRESS IN NUCLEAR ENERGY

Flow and heat transfer characteristics in an annulus wrapped with a helical wire

(2009) T. Sreenivasulu et al.   INTERNATIONAL JOURNAL OF THERMAL SCIENCES

SSTAR: The US lead-cooled fast reactor (LFR)

(2008) Craig F. Smith et al.   JOURNAL OF NUCLEAR MATERIALS