Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

Numerical study on the turbulent mixing in channel with Large Eddy Simulation (LES) using spectral element method

(2019) Haoran Ju et al.   NUCLEAR ENGINEERING AND DESIGN

An investigative study of enrichment reduction impact on the neutron flux in the in-core flux-trap facility of MTR research reactors

(2019) Ned Xoubi et al.   Nuclear Engineering and Technology

Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements

(2019) Linfeng Li et al.   ANNALS OF NUCLEAR ENERGY

An Assessment of Coupling Algorithms in HTR Simulator TINTE

(2018) Han Zhang et al.   NUCLEAR SCIENCE AND ENGINEERING

Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000

(2018) Xiaohan Zhao et al.   PROGRESS IN NUCLEAR ENERGY

A simulation of I2S-LWR selected transients

(2017) Andrew M. Ward et al.   ANNALS OF NUCLEAR ENERGY

Coupling of dynamic Monte Carlo with thermal-hydraulic feedback

(2015) Bart L. Sjenitzer et al.   ANNALS OF NUCLEAR ENERGY

Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor

(2015) Daxin Gong et al.   Science and Technology of Nuclear Installations

Development of a thermal–hydraulic analysis code for research reactors with plate fuels

(2009) Qing Lu et al.   ANNALS OF NUCLEAR ENERGY

MTR benchmark static calculations with MCNP5 code

(2007) Anis Bousbia-Salah et al.   ANNALS OF NUCLEAR ENERGY