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Disposal canister for spent nuclear fuel design report
Heikki Raiko
VTT Technical Research Centre of Finland
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Dive into the research topics of 'Disposal canister for spent nuclear fuel design report'. Together they form a unique fingerprint.
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Keyphrases
Canister
100%
Spent nuclear Fuel
100%
Fuel Design
100%
Disposal Canister
100%
Design Basis
15%
Fuel Assembly
15%
Finland
7%
Quality Requirements
7%
Corrosion Resistance
7%
Tight
7%
Quality Control
7%
Safety Factor
7%
Mechanical Strength
7%
Final Disposal
7%
Bentonite
7%
VVER-440
7%
Load Case
7%
Reactor Type
7%
Flow Channel
7%
Overpack
7%
Thermal Effect
7%
Radiation Dose Rate
7%
Swelling Pressure
7%
Oxygen-free Copper
7%
Compacted Graphite Iron
7%
Glaciation
7%
Radiolysis
7%
High Probability
7%
Engineering Safety
7%
Groundwater Pressure
7%
Elevated Hydrostatic Pressure
7%
INIS
spent fuels
100%
canisters
100%
design reports
100%
design
21%
fuels
21%
water
14%
copper
14%
fuel assemblies
14%
hydrostatics
14%
finland
7%
strains
7%
corrosion resistance
7%
reactors
7%
loading
7%
radiolysis
7%
oxygen
7%
capacity
7%
ground water
7%
graphite
7%
configuration
7%
voids
7%
probability
7%
quality control
7%
swelling
7%
bwr type reactors
7%
cast iron
7%
bentonite
7%
leakage
7%
wwer type reactors
7%
radiation doses
7%
thermal effects
7%
safety engineering
7%
dose rates
7%
Earth and Planetary Sciences
Can
100%
Nuclear Fuel
100%
Electron Paramagnetic Resonance
7%
Radiation Dose
7%
Hydrostatic Pressure
7%
Water Pressure
7%
Finland
7%
Bentonite
7%
Quality Control
7%
Corrosion Resistance
7%
Groundwater
7%
Radiolysis
7%
Engineering
Radiolysis
50%
Thermal Effect
50%