Experimental study of heat and mass transfer processes affecting the duration of operation of VVER passive core cooling systems

Lebezov, A.A.; Morozov, A.V.; Shlepkin, A.S.; Sakhipgareev, A.R.; Soshkina, A.S.

doi:10.1016/j.nucengdes.2024.112963

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

Supporting

Mentioning

Contrasting

Year Published

2024

2025

Publication Types

Select...

Article3

Preprint1

Relationship

Self Cite0

Independent4

Authors

Journals

Cited by 4 publications

References 20 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

The effects of different fuel cladding materials on neutronic behavior and fuel depletion performance in the VVER-1200 reactor

Kara,

Mammadzada

2025

Annals of Nuclear Energy

View full text Add to dashboard Cite

The effects of different fuel cladding materials on neutronic behavior and fuel depletion performance in the VVER-1200 reactor

Kara,

Mammadzada

2025

Annals of Nuclear Energy

View full text Add to dashboard Cite

Preface for special issue “Outcomes and achievements from researches orienting the future in nuclear fission technology: Russia, Kazakhstan, Uzbekistan”

Melikhov,

Tomahchik

2024

Nuclear Engineering and Design

View full text Add to dashboard Cite

Holistic Approach to Safety and Operational Stability: Analyzing VVER-1200 Reactor Dynamics in SGTR and AC Power Loss

Rah,

Joarder,

Hashan

et al. 2024

Preprint

View full text Add to dashboard Cite

VVER-1200 (Water-Water Energetic Reactor) represents a significant advancement in nuclear power generation, emphasizing the continuous analysis and enhancement of safety systems for reliable operation. The proposed study focuses on simulating combined scenarios involving steam generator tube rupture (SGTR) and AC power loss using core algorithms and models within personal computer transient analyzer (PCTRAN). Reactor kinetic equations, thermal-hydraulic balance, and safety system models are discussed to elucidate their role in simulating SGTR and AC power loss. Safety criteria, boundaries and initial conditions are outlined to provide a comprehensive understanding of the simulation framework. The analysis delves into dynamic behavior of VVER-1200, placing emphasis on thermal-hydraulic implications, essential reactor parameters, and radiation monitoring to facilitate impact evaluation. Continuous monitoring and maintenance of safety systems are underscored to ensure stable core cooling, particularly during proposed transient conditions. Through meticulous analysis and comparison with established benchmarks, this study contributes to bolstering the safety and reliability of VVER-1200 reactors by identifying vulnerabilities, assessing mitigation strategies, and refining emergency response protocols. Practical implications of this study offer a crucial understanding of reactor behavior, safety system performance, and emergency response strategies, thereby improving safety, optimizing operational practices, and reducing risks in nuclear reactor accidents.

show abstract

Experimental study of heat and mass transfer processes affecting the duration of operation of VVER passive core cooling systems

Cited by 4 publications

References 20 publications

The effects of different fuel cladding materials on neutronic behavior and fuel depletion performance in the VVER-1200 reactor

The effects of different fuel cladding materials on neutronic behavior and fuel depletion performance in the VVER-1200 reactor

Preface for special issue “Outcomes and achievements from researches orienting the future in nuclear fission technology: Russia, Kazakhstan, Uzbekistan”

Holistic Approach to Safety and Operational Stability: Analyzing VVER-1200 Reactor Dynamics in SGTR and AC Power Loss

Contact Info

Product

Resources

About