Research Topic

Thermal Hydraulics and Safety Analysis in Generation-IV Reactors

About this Research Topic

Generation-IV reactors have become a research hotspot among a huge number of national laboratories, universities and industries worldwide for nearly two decades since they were first proposed. Traditional thermal hydraulic and safety analysis becomes more complicated when applying to the Gen-IV reactors due to the different system design and operation mechanisms between Gen-IV reactors and traditional reactors, and also between different Gen-IV reactors. New technologies of thermal hydraulic analysis for both experiments and computation and new understanding of thermal hydraulic safety are desired for the development of Gen-IV reactors.

This Research Topic aims to provide the newest and most advanced research of thermal hydraulic and safety analysis of all Gen-IV reactors around the world. Innovative research including new experimental techniques, simulation models, theories, and research findings of Gen-IV reactors are welcomed.

In particular, the following themes are included:
• Special phenomena and mechanisms, including research on thermal hydraulic and safety phenomena and their mechanisms, such as the thermal stratification in the reactor pools, the heat transfer characteristics of low Pr number liquid metals, etc.
• Safety assessment and licensing technology, focusing on the Gen-IV reactors' safety principles, accidents classification, phenomena identification and ranking table (PIRT), and V&V methodology.
• Analysis methods and code development, primarily modeling method, system analysis method, sub-channel analysis method, and advanced numerical methods (eg. CFD), etc., and the corresponding analysis codes development for Gen-IV reactors.
• Innovative experiments for Gen-IV reactors, including fundamental thermal hydraulic experiments of advanced coolants, local phenomena experiments, integral experiments, and innovative measurement techniques.
• Safety system and advanced reactor design, including all kinds of Gen-IV reactors design, improvement and application.

Other topics not included but around these themes are also welcomed.


Keywords: thermal hydraulics, generation-IV reactors, safety analysis, multi-physics coupling, advanced numerical methods


Important Note: All contributions to this Research Topic must be within the scope of the section and journal to which they are submitted, as defined in their mission statements. Frontiers reserves the right to guide an out-of-scope manuscript to a more suitable section or journal at any stage of peer review.

Generation-IV reactors have become a research hotspot among a huge number of national laboratories, universities and industries worldwide for nearly two decades since they were first proposed. Traditional thermal hydraulic and safety analysis becomes more complicated when applying to the Gen-IV reactors due to the different system design and operation mechanisms between Gen-IV reactors and traditional reactors, and also between different Gen-IV reactors. New technologies of thermal hydraulic analysis for both experiments and computation and new understanding of thermal hydraulic safety are desired for the development of Gen-IV reactors.

This Research Topic aims to provide the newest and most advanced research of thermal hydraulic and safety analysis of all Gen-IV reactors around the world. Innovative research including new experimental techniques, simulation models, theories, and research findings of Gen-IV reactors are welcomed.

In particular, the following themes are included:
• Special phenomena and mechanisms, including research on thermal hydraulic and safety phenomena and their mechanisms, such as the thermal stratification in the reactor pools, the heat transfer characteristics of low Pr number liquid metals, etc.
• Safety assessment and licensing technology, focusing on the Gen-IV reactors' safety principles, accidents classification, phenomena identification and ranking table (PIRT), and V&V methodology.
• Analysis methods and code development, primarily modeling method, system analysis method, sub-channel analysis method, and advanced numerical methods (eg. CFD), etc., and the corresponding analysis codes development for Gen-IV reactors.
• Innovative experiments for Gen-IV reactors, including fundamental thermal hydraulic experiments of advanced coolants, local phenomena experiments, integral experiments, and innovative measurement techniques.
• Safety system and advanced reactor design, including all kinds of Gen-IV reactors design, improvement and application.

Other topics not included but around these themes are also welcomed.


Keywords: thermal hydraulics, generation-IV reactors, safety analysis, multi-physics coupling, advanced numerical methods


Important Note: All contributions to this Research Topic must be within the scope of the section and journal to which they are submitted, as defined in their mission statements. Frontiers reserves the right to guide an out-of-scope manuscript to a more suitable section or journal at any stage of peer review.

About Frontiers Research Topics

With their unique mixes of varied contributions from Original Research to Review Articles, Research Topics unify the most influential researchers, the latest key findings and historical advances in a hot research area! Find out more on how to host your own Frontiers Research Topic or contribute to one as an author.

Topic Editors

Loading..

Submission Deadlines

13 October 2020 Manuscript

Participating Journals

Manuscripts can be submitted to this Research Topic via the following journals:

Loading..

Topic Editors

Loading..

Submission Deadlines

13 October 2020 Manuscript

Participating Journals

Manuscripts can be submitted to this Research Topic via the following journals:

Loading..
Loading..

total views article views article downloads topic views

}
 
Top countries
Top referring sites
Loading..