Morris F. Osborne
Morris F. Osborne publishes mostly in Materials Chemistry, Aerospace Engineering and Safety, Risk, Reliability and Quality, on topics such as Nuclear Materials and Properties, Nuclear reactor physics and engineering and Nuclear and radioactivity studies.
- World rank
- #2,689,286 of 7,710,434 ranked researchers
- Rank in United States
- #784,924 of 1,627,098
- Works
- 86
- Citations
- 447
- Citations per work
- 5.2
What does Morris F. Osborne research?
Morris F. Osborne's work is mostly in Engineering (42%), Materials Science (37%), Chemistry (7%).
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 Sciences7587.2%
- Engineering3641.7%
- Materials Science3237.2%
- Chemistry66.6%
- Computer Science11.7%
- Everything else1011.1%
- Social Sciences11.7%
- 1Materials Chemistry37% of their works
- 2Aerospace Engineering28% of their works
- 3Safety, Risk, Reliability and Quality14% of their works
- 4Inorganic Chemistry7% of their works
- 5Economics and Econometrics2% of their works
- 6Artificial Intelligence2% of their works
Research topics
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Nuclear and radioactivity studies
- Radioactive element chemistry and processing
- Graphite, nuclear technology, radiation studies
- Fusion materials and technologies
- Nuclear Engineering Thermal-Hydraulics
- Educational Robotics and Engineering
Which keywords describe Morris F. Osborne's research?
The keywords of their largest research topics: Accident Tolerant Fuels, Fuel Cladding, Molten Salt, Nuclear Reactor, Nuclear Fuel, Radiation Protection, Actinides and Uranium.
- Robotics Programming
- Thermal-Hydraulic Analysis
- radiation damage
- Oxidation Behavior
- Uranium
- Radiation Protection
- Nuclear Reactor
- Fuel Cladding
- Accident Tolerant Fuels
- Molten Salt
- Nuclear Fuel
- Actinides
- Nuclear Graphite
- fusion materials
- Passive Systems
- Education
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.
All 16 words, with their numbers
- Accident Tolerant Fuels681 topic
- Fuel Cladding681 topic
- Molten Salt571 topic
- Nuclear Reactor571 topic
- Nuclear Fuel341 topic
- Radiation Protection341 topic
- Actinides151 topic
- Uranium151 topic
- Nuclear Graphite111 topic
- Oxidation Behavior111 topic
- fusion materials81 topic
- radiation damage81 topic
- Passive Systems51 topic
- Thermal-Hydraulic Analysis51 topic
- Education41 topic
- Robotics Programming41 topic
Where does Morris F. Osborne work?
Morris F. Osborne's main affiliation in the publication record is Oak Ridge National Laboratory, United States.
How many publications and citations does Morris F. Osborne have?
OpenAlex counts 86 works and 447 citations for Morris F. Osborne, an h-index of 11, ranking #2,689,286 of 7,710,434 researchers worldwide on the quality score.
Ranked on field-normalised 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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