Yu. G. Dragunov
Yu. G. Dragunov publishes mostly in Materials Chemistry, Aerospace Engineering and Mechanics of Materials, on topics such as Nuclear reactor physics and engineering, Graphite, nuclear technology, radiation studies and Nuclear Materials and Properties.
- World rank
- #1,903,996 of 7,710,434 ranked researchers
- Rank in Russia
- #5,691 of 179,717
- Works
- 85
- Citations
- 541
- Citations per work
- 6.4
What does Yu. G. Dragunov research?
Yu. G. Dragunov's work is mostly in Engineering (56%), Materials Science (30%).
Their six largest subfields, inside their fields and domains; the grey slice is everything else they publish. The interactive view splits every one of their works down to single topics.
The fields and subfields, with their numbers
- Physical Sciences7385.8%
- Engineering4755.8%
- Materials Science2630.0%
- Everything else1214.2%
- 1Materials Chemistry30% of their works
- 2Aerospace Engineering28% of their works
- 3Mechanics of Materials9% of their works
- 4Safety, Risk, Reliability and Quality9% of their works
- 5Mechanical Engineering6% of their works
- 6Electrical and Electronic Engineering5% of their works
Research topics
- Nuclear reactor physics and engineering
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Material Properties and Failure Mechanisms
- Nuclear Engineering Thermal-Hydraulics
- Engineering Diagnostics and Reliability
- Advanced Power Generation Technologies
Which keywords describe Yu. G. Dragunov's research?
The keywords of their largest research topics: Molten Salt, Nuclear Reactor, Hydrogen Embrittlement, Nuclear Graphite, Oxidation Behavior, Corrosion, Steel and Accident Tolerant Fuels.
- Steam Generation
- Deformation
- Passive Systems
- Gas Pipeline
- Nuclear Fuel
- Accident Tolerant Fuels
- Corrosion
- Nuclear Graphite
- Nuclear Reactor
- Molten Salt
- Hydrogen Embrittlement
- Oxidation Behavior
- Steel
- Fuel Cladding
- Radiation Protection
- Material Degradation
- Thermal-Hydraulic Analysis
- Pipeline
- Thermal Conductivity
Size is their works in the topics tagged with each word, from their 8 largest topics. Each links to the topic it comes from most. The words come from the keyword list OpenAlex gives each topic, not from the text of the papers, so a word can appear that none of the papers uses.
All 19 words, with their numbers
- Molten Salt421 topic
- Nuclear Reactor421 topic
- Hydrogen Embrittlement382 topics
- Nuclear Graphite301 topic
- Oxidation Behavior301 topic
- Corrosion282 topics
- Steel282 topics
- Accident Tolerant Fuels221 topic
- Fuel Cladding221 topic
- Nuclear Fuel201 topic
- Radiation Protection201 topic
- Gas Pipeline161 topic
- Material Degradation161 topic
- Passive Systems141 topic
- Thermal-Hydraulic Analysis141 topic
- Deformation121 topic
- Pipeline121 topic
- Steam Generation111 topic
- Thermal Conductivity111 topic
Where does Yu. G. Dragunov work?
Yu. G. Dragunov's main affiliation in the publication record is Gidropribor, Russia.
How many publications and citations does Yu. G. Dragunov have?
OpenAlex counts 85 works and 541 citations for Yu. G. Dragunov, an h-index of 13, ranking #1,903,996 of 7,710,434 researchers worldwide on the quality score.
Ranked on field-normalised citation excellence (50%), output (30%) and citations (20%). Counts come from OpenAlex author records, which occasionally merge different people who share a name or split one person into several.
Papers, co-authors, who cited this work and researchers on the nearest topics have tabs of their own, above. Is this your page? Claim it with your ORCID iD, or request a correction or removal.
Discussion
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