Research graph
References from Preliminary conceptual design of a micro supercritical CO2-cooled pressure-tube reactor for unmanned underwater vehicles. Local targets link to admitted publications; unresolved targets remain external evidence.
Review of supercritical CO2 power cycle technology and current status of research and development
10.1016/j.net.2015.06.009 · 2015 · External 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 · 2022 · External reference
Selection of fuel cladding material for nuclear fission reactors
10.1016/j.engfailanal.2011.06.010 · 2011 · External reference
Mechanism analysis of convective heat transfer of supercritical CO2 in heated vertical-flow tube
10.1016/j.supflu.2025.106586 · 2025 · External reference
development trend of military UUV(Ⅰ): a review of U.S. Military Unmanned System Development Plan
2017 · External 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 · 2016 · External reference
Optimized core design of a supercritical carbon dioxide-cooled fast reactor
10.13182/nt08-a4030 · 2008 · External reference
Preliminary conceptual design and analysis of a 100 kWe level nuclear silent thermal‐electrical reactor (NUSTER‐100)
10.1002/er.8542 · 2022 · External reference
Unresolved reference
External reference
Tensile and creep properties of an oxide dispersion-strengthened ferritic steel
10.1016/s0022-3115(02)01046-2 · 2002 · External reference
Oxide dispersion-strengthened steels: a comparison of some commercial and experimental alloys
10.1016/j.jnucmat.2005.01.017 · 2005 · External reference
Study on reactivity control strategies for the thermoelectric integrated space nuclear reactor
10.1016/j.anucene.2020.107607 · 2020 · External reference
Preliminary no-core melt assessment for the high-efficiency channel preconceptual design
2012 · External reference
Unresolved reference
External reference
Flow mixing and heat transfer deterioration investigation of supercritical carbon dioxide in wire-wrapped bundles
10.1016/j.applthermaleng.2024.123569 · 2024 · External reference
High temperature mechanical properties and microstructure in 9Cr or 12Cr oxide dispersion strengthened steels
10.2355/tetsutohagane.tetsu-2022-080 · 2023 · External reference
Unresolved reference
External reference
Unresolved reference
1996 · External reference
Supercritical CO2 Direct Cycle Gas Fast Reactor (SC-GFR) Concept (No. SAND2011-1804C). Sandia National Lab
2010 · External reference
A comprehensive review of unmanned underwater vehicles: technologies, applications, and challenges
2025 · External reference
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
10.1016/j.net.2021.09.030 · 2022 · External reference
Unresolved reference
External reference
OpenMC: a state-of-the-art Monte Carlo code for research and development
10.1016/j.anucene.2014.07.048 · 2015 · External reference
Reactivity control options of space nuclear reactors
10.1016/j.pnucene.2008.11.003 · 2009 · External reference
Unresolved reference
External reference
Reactor core design and analysis for a micronuclear power source
10.3389/fenrg.2018.00014 · 2018 · External reference
Unit mechanisms of fission gas release: current understanding and future needs
10.1016/j.jnucmat.2018.03.016 · 2018 · External reference
Materials for future nuclear energy systems
10.1016/j.jnucmat.2019.151837 · 2019 · External reference
Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario
10.1016/j.anucene.2015.03.006 · 2015 · External reference
Conceptual design of a MW heat pipe reactor
10.1016/j.net.2024.02.009 · 2024 · External reference
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions
10.1016/j.jnucmat.2017.02.021 · 2017 · External reference
Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis
10.13182/nt14-22 · 2014 · External reference
A conceptual study of a supercritical CO2-cooled micro modular reactor
10.3390/en81212405 · 2015 · External reference
Development of nuclear fuel for space power reactor
2019 · External reference
Current state and prospect on the development of advanced nuclear fuel system materials: a review
2021 · External reference
Core physical conceptual design of small reactor for unmanned underwater vehicle
10.1016/j.nucengdes.2022.111663 · 2022 · External reference
Preliminary conceptual design and analysis of a 100 kWe level nuclear silent thermal‐electrical reactor (NUSTER‐100)
10.1002/er.8542 · ExternalCitation · doi-reference
OpenMC: a state-of-the-art Monte Carlo code for research and development
10.1016/j.anucene.2014.07.048 · ExternalCitation · doi-reference
Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario
10.1016/j.anucene.2015.03.006 · ExternalCitation · doi-reference
Study on reactivity control strategies for the thermoelectric integrated space nuclear reactor
10.1016/j.anucene.2020.107607 · ExternalCitation · doi-reference
Flow mixing and heat transfer deterioration investigation of supercritical carbon dioxide in wire-wrapped bundles
10.1016/j.applthermaleng.2024.123569 · ExternalCitation · doi-reference
Selection of fuel cladding material for nuclear fission reactors
10.1016/j.engfailanal.2011.06.010 · ExternalCitation · doi-reference
Oxide dispersion-strengthened steels: a comparison of some commercial and experimental alloys
10.1016/j.jnucmat.2005.01.017 · ExternalCitation · doi-reference
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions
10.1016/j.jnucmat.2017.02.021 · ExternalCitation · doi-reference
Unit mechanisms of fission gas release: current understanding and future needs
10.1016/j.jnucmat.2018.03.016 · ExternalCitation · doi-reference
Materials for future nuclear energy systems
10.1016/j.jnucmat.2019.151837 · ExternalCitation · doi-reference
Review of supercritical CO2 power cycle technology and current status of research and development
10.1016/j.net.2015.06.009 · ExternalCitation · doi-reference
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
10.1016/j.net.2021.09.030 · ExternalCitation · doi-reference
Conceptual design of a MW heat pipe reactor
10.1016/j.net.2024.02.009 · ExternalCitation · 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 · ExternalCitation · doi-reference
Core physical conceptual design of small reactor for unmanned underwater vehicle
10.1016/j.nucengdes.2022.111663 · ExternalCitation · doi-reference
Reactivity control options of space nuclear reactors
10.1016/j.pnucene.2008.11.003 · ExternalCitation · doi-reference
Mechanism analysis of convective heat transfer of supercritical CO2 in heated vertical-flow tube
10.1016/j.supflu.2025.106586 · ExternalCitation · doi-reference
Tensile and creep properties of an oxide dispersion-strengthened ferritic steel
10.1016/s0022-3115(02)01046-2 · ExternalCitation · 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 · ExternalCitation · doi-reference
Optimized core design of a supercritical carbon dioxide-cooled fast reactor
10.13182/nt08-a4030 · ExternalCitation · doi-reference
Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis
10.13182/nt14-22 · ExternalCitation · doi-reference
High temperature mechanical properties and microstructure in 9Cr or 12Cr oxide dispersion strengthened steels
10.2355/tetsutohagane.tetsu-2022-080 · ExternalCitation · doi-reference
Reactor core design and analysis for a micronuclear power source
10.3389/fenrg.2018.00014 · ExternalCitation · doi-reference
A conceptual study of a supercritical CO2-cooled micro modular reactor
10.3390/en81212405 · ExternalCitation · doi-reference
