Heat pipe failure accident analysis in megawatt heat pipe cooled reactor

Neutronics and thermal-hydraulics coupling analysis in accelerator-driven subcritical system

(2020) Yugao Ma et al.   PROGRESS IN NUCLEAR ENERGY

Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor

(2020) Xiao Liu et al.   ANNALS OF NUCLEAR ENERGY

Thermal‐hydraulic design features of a micronuclear reactor power source applied for multipurpose

(2019) Xiao Liu et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

RMC/CTF multiphysics solutions to VERA core physics benchmark problem 9

(2019) Yugao Ma et al.   ANNALS OF NUCLEAR ENERGY

Experimental study on startup performance of high temperature potassium heat pipe at different inclination angles and input powers for nuclear reactor application

(2019) Chenglong Wang et al.   ANNALS OF NUCLEAR ENERGY

Conceptual design and analysis of a multipurpose micro nuclear reactor power source

(2018) Hao Sun et al.   ANNALS OF NUCLEAR ENERGY

Analysis of BEAVRS two-cycle benchmark using RMC based on full core detailed model

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

Development of on-the-fly temperature-dependent cross-sections treatment in RMC code

(2016) Shichang Liu et al.   ANNALS OF NUCLEAR ENERGY

RMC – A Monte Carlo code for reactor core analysis

(2015) Kan Wang et al.   ANNALS OF NUCLEAR ENERGY