Page 21 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
P. 21
xx Nomenclature
complementary metal oxide semiconductor
CMOS
carbon dioxide
CO 2
water model of EFR cold pool
COCO
water model of EFR hot pool
COLCHIX
COMponent LOop Testing
COMPLOT
corrosion in dynamic alloys
CORRIDA
central processing unit
CPU
chromium
Cr
Corrosion Research for Advanced Fast reactor Technologies
CRAFT
Clinch River breeder reactor project
CRBRP
core simulator
CS
computational structural mechanics
CSM
copper
Cu
discrete element method
DEM
detached eddy simulation
DES
Dounreay Fast Reactor
DFR
decay heat removal
DHR
DIvertor TEst FAcility
DITEFA
direct numerical simulation
DNS
Department of Energy
DOE
experimental breeder reactor
EBR
eddy diffusivity model
EDM
European fast reactor
EFR
extraneously induced excitations
EIE
Roadmap for a European Innovative SOdium-cooled FAst Reactor
EISOFAR
European Lead Fast Reactor
ELFR
European Lead-cooled SYstem
ELSY
electromagnetic
EM
equation of state
EOS
European SCAled Pool Experiment
ESCAPE
European Sodium Fast Reactor
ESFR
European Sodium Fast Reactor Safety Measures Assessment and
ESFR-SMART
Research Tools
European Sustainable Nuclear Industrial Initiative
ESNII
preparing ESNII for HORIZON 2020
ESNII+
Euler number
Eu
European research program for transmutation of high level nuclear waste in
EUROTRANS
an ADS
fluid to solid
F2S
Fostering ALfred CONstruction
FALCON
fiber Bragg gratings
FBG
fast breeder test reactor
FBTR
finite element analysis
FEA
fluorinated poly(ethylene-propylene)
FEP
flow-induced vibration
FIV
flat linear induction pump
FLIP
fast Fourier transform
FFT
fast flux test facility
FFTF
fuel pin simulator/functional performance specification
FPS