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Nuclear Technology

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Advancements in Experimental and Numerical Research on Safety Related Thermal Hydraulics in Nuclear Reactors and Utilities

Manuscript deadline
31 December 2024

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Article collection guest advisor(s)

Associate Professor Kai Wang, Sun Yat-sen University
[email protected]

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Advancements in Experimental and Numerical Research on Safety Related Thermal Hydraulics in Nuclear Reactors and Utilities

Safety-related thermal-hydraulics in nuclear reactors and utilities is a critical area of research that focuses on analyzing the behavior of fluids and heat transfer mechanisms to ensure the safe operation of nuclear systems. This encompasses the study of coolant flow patterns, heat removal capabilities, and safety protocols under both normal operating conditions and hypothetical accident scenarios. Understanding and optimizing safety-related thermal-hydraulics is paramount in safeguarding nuclear facilities against potential hazards and ensuring public and environmental safety.

The safety-related thermal-hydraulics in nuclear reactors and utilities directly impacts reactor safety, emergency response capabilities, and overall risk mitigation strategies. By comprehensively analyzing thermal-hydraulic phenomena such as core cooling, containment integrity, and heat transfer characteristics, researchers and engineers can develop robust safety measures and protocols to prevent accidents, mitigate consequences in the event of unforeseen incidents, and enhance the overall reliability and resilience of nuclear facilities.

This special collection aims to showcase advancements in experimental and numerical research specifically focused on safety-related thermal-hydraulics in nuclear reactors and utilities. The subtopics within this scope include safety analysis of reactor cores, accident mitigation strategies, safety assessments for nuclear utilities, and advanced numerical simulations validated through experimental data. We welcome original research articles, review papers, and technical notes that contribute to enhancing our understanding of safety-related thermal-hydraulics and promoting best practices in nuclear reactor and utilities safety and reliability.


All manuscripts submitted to this Article Collection will undergo desk assessment and peer-review as part of our standard editorial process. Guest Advisors will not be involved in peer-reviewing manuscripts unless they are an existing member of the Editorial Board.

Please review the journal scope and author submission instructions prior to submitting a manuscript.

The deadline for submitting manuscripts is 31 December 2024.

Please contact Agnes Zhou at [email protected] with any queries regarding this Article Collection.

For Taylor and Francis Journals: Please be sure to select the appropriate Article Collection from the drop-down menu in the submission system.

 

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All manuscripts submitted to this Article Collection will undergo desk assessment and peer-review as part of our standard editorial process. Guest Advisors for this collection will not be involved in peer-reviewing manuscripts unless they are an existing member of the Editorial Board. Please review the journal Aims and Scope and author submission instructions prior to submitting a manuscript.