Works matching AU Cao, Liangzhi
Results: 9
SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities.
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- Energies (19961073), 2020, v. 13, n. 20, p. 5410, doi. 10.3390/en13205410
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- Article
A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR.
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- Energies (19961073), 2020, v. 13, n. 16, p. 4070, doi. 10.3390/en13164070
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- Article
Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0.
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- EPJ Nuclear Sciences & Technologies, 2024, v. 10, p. 1, doi. 10.1051/epjn/2024014
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- Article
Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors.
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- International Journal of Energy Research, 2021, v. 45, n. 8, p. 11677, doi. 10.1002/er.5490
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- Article
Conceptual core design study of an innovative small transportable lead‐bismuth cooled fast reactor (SPARK) for remote power supply.
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- International Journal of Energy Research, 2018, v. 42, n. 11, p. 3672, doi. 10.1002/er.4119
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- Article
Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code.
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- International Journal of Energy Research, 2018, v. 42, n. 1, p. 261, doi. 10.1002/er.3828
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- Article
Reactor core transient analysis of an innovative high-level nuclear waste transmuter with metal fuel.
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- International Journal of Energy Research, 2017, v. 41, n. 9, p. 1322, doi. 10.1002/er.3715
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- Article
Subchannel Analysis, CFD Modeling and Verifications, CHF Experiments and Benchmarking.
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- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/209747
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- Article
Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/698019
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- Article