M. Grivé
M. Grivé publishes mostly in Inorganic Chemistry, Materials Chemistry and Global and Planetary Change, on topics such as Radioactive element chemistry and processing, Nuclear Materials and Properties and Nuclear materials and radiation effects.
- World rank
- #4,326,038 of 7,710,434 ranked researchers
- Rank in Spain
- #99,391 of 204,306
- Works
- 64
- Citations
- 1.3k
- Citations per work
- 19.7
What does M. Grivé research?
M. Grivé's work is mostly in Chemistry (25%), Materials Science (24%), Environmental Science (13%).
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 Sciences4569.8%
- Chemistry1625.1%
- Materials Science1524.0%
- Environmental Science812.8%
- Engineering57.9%
- Everything else1930.2%
- 1Inorganic Chemistry25% of their works
- 2Materials Chemistry24% of their works
- 3Global and Planetary Change7% of their works
- 4Industrial and Manufacturing Engineering6% of their works
- 5Civil and Structural Engineering4% of their works
- 6Aerospace Engineering3% of their works
Research topics
- Radioactive element chemistry and processing
- Nuclear Materials and Properties
- Nuclear materials and radiation effects
- Radioactive contamination and transfer
- Chemical Synthesis and Characterization
- Graphite, nuclear technology, radiation studies
- Nuclear reactor physics and engineering
- Concrete and Cement Materials Research
Which keywords describe M. Grivé's research?
The keywords of their largest research topics: Actinides, Adsorption, Lanthanides, Uranium, Accident Tolerant Fuels, Fuel Cladding, Nuclear Waste Disposal and Pyrochlore.
- Nuclear Reactor
- Geopolymer
- Oxidation Behavior
- Ion Exchange
- nuclear accident
- Pyrochlore
- Fuel Cladding
- Uranium
- Adsorption
- Actinides
- Lanthanides
- Accident Tolerant Fuels
- Nuclear Waste Disposal
- Fukushima Daiichi
- Cesium Removal
- Nuclear Graphite
- Cementitious Materials
- Molten Salt
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 18 words, with their numbers
- Actinides582 topics
- Adsorption552 topics
- Lanthanides451 topic
- Uranium451 topic
- Accident Tolerant Fuels181 topic
- Fuel Cladding181 topic
- Nuclear Waste Disposal131 topic
- Pyrochlore131 topic
- Fukushima Daiichi111 topic
- nuclear accident111 topic
- Cesium Removal101 topic
- Ion Exchange101 topic
- Nuclear Graphite71 topic
- Oxidation Behavior71 topic
- Cementitious Materials61 topic
- Geopolymer61 topic
- Molten Salt61 topic
- Nuclear Reactor61 topic
Where does M. Grivé work?
M. Grivé's main affiliation in the publication record is Amphos 21 (Spain), Spain.
How many publications and citations does M. Grivé have?
OpenAlex counts 64 works and 1,262 citations for M. Grivé, an h-index of 18, ranking #4,326,038 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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