HEART, a specific code for thermal-electrical analysis of heat pipe cooled nuclear reactor

Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor

(2021) Zeqin Zhang et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor

(2021) Yin ZHANG et al.   APPLIED THERMAL ENGINEERING

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

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

NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems

(2020) Qingming He et al.   ANNALS OF NUCLEAR ENERGY

Transient thermal-hydraulic analysis of thermionic space reactor TOPAZ-II with modified RELAP5

(2019) Simiao Tang et al.   PROGRESS IN NUCLEAR ENERGY

Influence of geometric parameter on the performance of a new asymmetrical and segmented thermoelectric generator

(2019) Dhruv Raj Karana et al.   ENERGY

Study on startup characteristics of heat pipe cooled and AMTEC conversion space reactor system

(2016) Yuan Yuan et al.   PROGRESS IN NUCLEAR ENERGY