Advanced nuclear reactors and relative energy transport systems are attracting wide attention in the world. Those reactors include Gas-cooled reactors, Metal (Lead, Lead-bismuth, Sodium) cooled reactors, Heat pipe reactors, Water cooled reactors and so on. Innovations and profound research works (including experimental and numerical research) about complex flow and heat transfer in nuclear energy systems are desired to support advancements of those reactor technologies to meet the goals of sustainability, safety and reliability.
The Research Topic “Complex Flow and Heat Transfer in Advanced Nuclear Energy systems” aims to collect and publish new research works about complex flow and heat transfer in nuclear energy systems. Those research will be experimental research or numerical simulation about complex flow and heat transfer in the nuclear reactor core or important equipment in nuclear energy transport systems, such as heat exchanger, loop design, flow stability, two-phase or supercritical phenomena/techniques. Also, this themed issue will include those new technological researches about heat transfer enhancement, experiment or numerical simulation methods and system analysis.
The Research Topic includes but is not limited to the following:
(1) experiment research about flow and heat transfer in nuclear energy systems
(2) numerical research about flow and heat transfer in nuclear energy systems
(3) method of experimental/numerical research on thermal hydraulics
(4) system analysis of nuclear energy transport system
(5) nuclear energy system related complex heat transfer phenomena, stability, measurement techniques, data processing techniques, etc.
Advanced nuclear reactors and relative energy transport systems are attracting wide attention in the world. Those reactors include Gas-cooled reactors, Metal (Lead, Lead-bismuth, Sodium) cooled reactors, Heat pipe reactors, Water cooled reactors and so on. Innovations and profound research works (including experimental and numerical research) about complex flow and heat transfer in nuclear energy systems are desired to support advancements of those reactor technologies to meet the goals of sustainability, safety and reliability.
The Research Topic “Complex Flow and Heat Transfer in Advanced Nuclear Energy systems” aims to collect and publish new research works about complex flow and heat transfer in nuclear energy systems. Those research will be experimental research or numerical simulation about complex flow and heat transfer in the nuclear reactor core or important equipment in nuclear energy transport systems, such as heat exchanger, loop design, flow stability, two-phase or supercritical phenomena/techniques. Also, this themed issue will include those new technological researches about heat transfer enhancement, experiment or numerical simulation methods and system analysis.
The Research Topic includes but is not limited to the following:
(1) experiment research about flow and heat transfer in nuclear energy systems
(2) numerical research about flow and heat transfer in nuclear energy systems
(3) method of experimental/numerical research on thermal hydraulics
(4) system analysis of nuclear energy transport system
(5) nuclear energy system related complex heat transfer phenomena, stability, measurement techniques, data processing techniques, etc.