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Zhuhan Ran, Pan Wu, JianQiang Shan
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Review of supercritical CO2 power cycle technology and current status of research and development
10.1016/j.net.2015.06.009 · 2015
Radiative heat transfer analysis of 37-pin fuel bundle of Indian pressurized heavy water reactor under heat-up condition: experimental, numerical and analytical study
10.1080/15567036.2020.1819479 · 2022
Selection of fuel cladding material for nuclear fission reactors
10.1016/j.engfailanal.2011.06.010 · 2011
Mechanism analysis of convective heat transfer of supercritical CO2 in heated vertical-flow tube
10.1016/j.supflu.2025.106586 · 2025
development trend of military UUV(Ⅰ): a review of U.S. Military Unmanned System Development Plan
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An experimental investigation of supercritical heat transfer in a three-rod bundle equipped with wire-wrap and grid spacers and cooled by carbon dioxide
10.1016/j.nucengdes.2016.04.002 · 2016
Optimized core design of a supercritical carbon dioxide-cooled fast reactor
10.13182/nt08-a4030 · 2008
Preliminary conceptual design and analysis of a 100 kWe level nuclear silent thermal‐electrical reactor (NUSTER‐100)
10.1002/er.8542 · 2022
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Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions
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Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis
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Core physical conceptual design of small reactor for unmanned underwater vehicle
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A conceptual study of a supercritical CO2-cooled micro modular reactor
10.3390/en81212405 · doi-reference
Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis
10.13182/nt14-22 · doi-reference
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions
10.1016/j.jnucmat.2017.02.021 · doi-reference
Conceptual design of a MW heat pipe reactor
10.1016/j.net.2024.02.009 · doi-reference
Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario
10.1016/j.anucene.2015.03.006 · doi-reference
Materials for future nuclear energy systems
10.1016/j.jnucmat.2019.151837 · doi-reference
Unit mechanisms of fission gas release: current understanding and future needs
10.1016/j.jnucmat.2018.03.016 · doi-reference
Reactor core design and analysis for a micronuclear power source
10.3389/fenrg.2018.00014 · doi-reference
Reactivity control options of space nuclear reactors
10.1016/j.pnucene.2008.11.003 · doi-reference
OpenMC: a state-of-the-art Monte Carlo code for research and development
10.1016/j.anucene.2014.07.048 · doi-reference
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
10.1016/j.net.2021.09.030 · doi-reference
High temperature mechanical properties and microstructure in 9Cr or 12Cr oxide dispersion strengthened steels
10.2355/tetsutohagane.tetsu-2022-080 · doi-reference
Flow mixing and heat transfer deterioration investigation of supercritical carbon dioxide in wire-wrapped bundles
10.1016/j.applthermaleng.2024.123569 · doi-reference
Study on reactivity control strategies for the thermoelectric integrated space nuclear reactor
10.1016/j.anucene.2020.107607 · doi-reference
Oxide dispersion-strengthened steels: a comparison of some commercial and experimental alloys
10.1016/j.jnucmat.2005.01.017 · doi-reference
Tensile and creep properties of an oxide dispersion-strengthened ferritic steel
10.1016/s0022-3115(02)01046-2 · doi-reference
Preliminary conceptual design and analysis of a 100 kWe level nuclear silent thermal‐electrical reactor (NUSTER‐100)
10.1002/er.8542 · doi-reference
Optimized core design of a supercritical carbon dioxide-cooled fast reactor
10.13182/nt08-a4030 · doi-reference
An experimental investigation of supercritical heat transfer in a three-rod bundle equipped with wire-wrap and grid spacers and cooled by carbon dioxide
10.1016/j.nucengdes.2016.04.002 · doi-reference
Mechanism analysis of convective heat transfer of supercritical CO2 in heated vertical-flow tube
10.1016/j.supflu.2025.106586 · doi-reference
Selection of fuel cladding material for nuclear fission reactors
10.1016/j.engfailanal.2011.06.010 · doi-reference
Radiative heat transfer analysis of 37-pin fuel bundle of Indian pressurized heavy water reactor under heat-up condition: experimental, numerical and analytical study
10.1080/15567036.2020.1819479 · doi-reference
Review of supercritical CO2 power cycle technology and current status of research and development
10.1016/j.net.2015.06.009 · doi-reference