Skip to main navigation
Skip to search
Skip to main content
VTT's Research Information Portal Home
Search content at VTT's Research Information Portal
Home
Profiles
Research output
Projects
Datasets
Research units
Research Infrastructures
Activities
Prizes
Press/Media
Impacts
An autoclave system for uranium oxide dissolution experiments
Mikko Nykyri
VTT Technical Research Centre of Finland
Research output
:
Book/Report
›
Report
Overview
Fingerprint
Fingerprint
Dive into the research topics of 'An autoclave system for uranium oxide dissolution experiments'. Together they form a unique fingerprint.
Sort by
Weight
Alphabetically
Keyphrases
Finland
100%
Autoclave
100%
Oxide Dissolution
100%
Dissolution Test
100%
Uranium Oxide
100%
Supply Vessel
66%
Groundwater
33%
Technical Research
33%
Final Disposal
33%
Spent Fuel
33%
High Pressure
33%
Dissolution Rate
33%
Elevated Temperature
33%
Low Oxygen Content
33%
Nuclear Energy
33%
Spent nuclear Fuel
33%
Temperature Variation
33%
Potential Measure
33%
Electrolyte
33%
Polytetrafluoroethylene
33%
Pressure Balance
33%
Pressure Vessel
33%
Granitic Bedrock
33%
Reference Electrode
33%
Fuel Pellets
33%
Nitrogen Gas
33%
Pressure Variation
33%
Risk Analysis Model
33%
State Council
33%
Redox Electrode
33%
Platinum Wire
33%
Operation Limit
33%
Oxide Matrix
33%
Energy Producers
33%
Measuring Electrode
33%
Water Exchange
33%
Preparation Phase
33%
Ag@AgCl
33%
Deoxygenated
33%
Engineering
Technical Research Centre
100%
Spent Fuels
100%
Final Disposal
100%
Dissolution Rate
100%
Elevated Temperature
100%
Spent Nuclear Fuel
100%
Prevailing Condition
100%
Fuel Pellet
100%
Preparation Phase
100%
Pressure Vessel
100%
Nuclear Energy
100%
Oxygen Content
100%
INIS
dissolution
100%
vessels
100%
autoclaves
100%
uranium oxides
100%
water
66%
finland
50%
electrodes
50%
supply
33%
spent fuels
33%
simulation
16%
operation
16%
wires
16%
pressure range mega pa
16%
variations
16%
gases
16%
matrices
16%
oxygen
16%
ground water
16%
nitrogen
16%
platinum
16%
high pressure
16%
electrolytes
16%
pressure vessels
16%
risk analysis
16%
nuclear energy
16%
fuel pellets
16%
polytetrafluoroethylene
16%
silver chlorides
16%
Material Science
Uranium Oxide
100%
Platinum
50%
Nuclear Fuel
50%
Chemical Engineering
Polytetrafluoroethylene
100%