Frédérique Rossillon
Frédérique Rossillon publishes mostly in Mechanical Engineering, Materials Chemistry and Aerospace Engineering, on topics such as Nuclear reactor physics and engineering, Welding Techniques and Residual Stresses and Graphite, nuclear technology, radiation studies.
- World rank
- #6,645,205 of 7,710,434 ranked researchers
- Rank in France
- #284,374 of 324,115
- Works
- 28
- Citations
- 19
- Citations per work
- 0.7
What does Frédérique Rossillon research?
Frédérique Rossillon's work is mostly in Engineering (55%), Materials Science (16%), Chemistry (4%).
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 Sciences2175.4%
- Engineering1554.9%
- Materials Science516.4%
- Chemistry14.1%
- Everything else724.6%
- 1Mechanical Engineering29% of their works
- 2Materials Chemistry16% of their works
- 3Aerospace Engineering11% of their works
- 4Mechanics of Materials10% of their works
- 5Safety, Risk, Reliability and Quality6% of their works
- 6Spectroscopy4% of their works
Research topics
- Nuclear reactor physics and engineering
- Welding Techniques and Residual Stresses
- Graphite, nuclear technology, radiation studies
- Fatigue and fracture mechanics
- Microstructure and Mechanical Properties of Steels
- Advanced Welding Techniques Analysis
- Nuclear and radioactivity studies
- Nuclear Materials and Properties
Which keywords describe Frédérique Rossillon's research?
The keywords of their largest research topics: Microstructure, Molten Salt, Nuclear Graphite, Nuclear Reactor, Oxidation Behavior, Residual Stress, Welding and Fatigue Crack Closure.
- Accident Tolerant Fuels
- Processing
- Martensite Transformation
- Friction Stir Welding
- Fatigue Crack Closure
- Residual Stress
- Nuclear Reactor
- Molten Salt
- Microstructure
- Nuclear Graphite
- Oxidation Behavior
- Welding
- Fracture Toughness Testing
- High-Strength Steels
- Nuclear Fuel
- Radiation Protection
- Fuel Cladding
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 17 words, with their numbers
- Microstructure82 topics
- Molten Salt61 topic
- Nuclear Graphite61 topic
- Nuclear Reactor61 topic
- Oxidation Behavior61 topic
- Residual Stress61 topic
- Welding61 topic
- Fatigue Crack Closure51 topic
- Fracture Toughness Testing51 topic
- Friction Stir Welding41 topic
- High-Strength Steels41 topic
- Martensite Transformation41 topic
- Nuclear Fuel41 topic
- Processing41 topic
- Radiation Protection41 topic
- Accident Tolerant Fuels31 topic
- Fuel Cladding31 topic
Where does Frédérique Rossillon work?
Frédérique Rossillon's main affiliation in the publication record is Forum Réfugiés - Cosi, France.
How many publications and citations does Frédérique Rossillon have?
OpenAlex counts 28 works and 19 citations for Frédérique Rossillon, an h-index of 2, ranking #6,645,205 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.
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