HEART, a specific code for thermal-electrical analysis of heat pipe cooled nuclear reactor-Reference-Cited by-同舟云学术

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

Published:2022-09 Issue: Volume:179 Page:107666
ISSN:1290-0729
Container-title:International Journal of Thermal Sciences
language:en
Short-container-title:International Journal of Thermal Sciences

Author:

Zhang Zeqin^ORCID,Wang Chenglong^ORCID,Guo Kailun,Huang Jinlu,Qiu Suizheng,Su G.H.,Tian Wenxi

Funder

National Key Research and Development Program of China

Science Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China

Publisher

Elsevier BV

Subject

General Engineering,Condensed Matter Physics

Reference21 articles.

1. SNAP (Space Nuclear Auxiliary Power) Reactor Overview;Voss,1984

2. Transient thermal-hydraulic analysis of thermionic space reactor TOPAZ-II with modified RELAP5;Tang;Prog. Nucl. Energy,2019

3. Thermal-hydraulic Analysis of a New Conceptual Heat Pipe Cooled Small Nuclear Reactor System;Wang,2020

4. The Heatpipe-Operated Mars Exploration Reactor (HOMER);Poston,2000

5. The Martian Surface Reactor: an Advanced Nuclear Power Station for Manned Extraterrestrial Exploration;Bushman,2004

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1. Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL;Annals of Nuclear Energy;2024-12

2. Direct numerical simulations of pool boiling in presence of a uniform electric field on nonideal surfaces with contact angle hysteresis;International Journal of Thermal Sciences;2024-11

3. Study on operation characteristics of a compact megawatt nuclear power system;Annals of Nuclear Energy;2024-04

4. Active fault tolerant control of a heat pipe-cooled reactor based on state feedback method;Nuclear Engineering and Design;2024-04

5. Study on start-up characteristics of a heat pipe cooled reactor coupled with a supercritical CO2 Brayton cycle;Applied Thermal Engineering;2024-01

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