Page 22 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Nomenclature xxi

fluid-structure interaction
FSI
generation
Gen
generalized gradient diffusion hypothesis
GGDH
Generation IV International Forum
GIF
Grash of number
Gr
water
H 2 O
heavy liquid metal network
HeLiMNet
mercury
Hg
heavy liquid metal
HLM
high-performance computing
HPC
high-temperature reactor
HTR
heat exchanger
HX
International Atomic Energy Agency
IAEA
integral effect test
IET
instability-induced excitations
IIE
interface quasi-Newton with inverse Jacobian from a least squares model
IQN-ILS
integral test
IT
in-vessel melt retention
IVMR
in-vessel retention
IVR
water model of EFR hot pool
JESSICA
Japanese sodium fast reactor
JSFR
KArlsruhe Liquid metal LAboratory
KALLA
Karlsruhe Sodium Laboratory
KASOLA
Kompakte Natriumgek€ uhlte Kernreaktoranlage Karlsruhe (German)
KNK
Los Alamos Molten Plutonium Reactor Experiment
LAMPRE
lead-bismuth eutectic
LBE
laser Doppler anemometry
LDA
laser Doppler velocimetry
LDV
Lead-cooled European Advanced DEmonstration Reactor
LEADER
LEad CORrosion
LECOR
large eddy simulation
LES
lead-cooled fast reactor
LFR
Lorentz force velocimetry
LFV
laser-induced fluorescence
LIF
Liquid Metal Model for Continuous CASTing
LIMMCAST
liquid metal
LM
liquid-metal reactor
LMR
liquid-metal fast reactor
LMFR
loss-of-coolant accident
LOCA
light-water reactor
LWR
Methodology, Analysis, and eXperiments for the Safety In MYRRHA
MAXSIMA
Assessment
mechanical pump
MCP
Magnetohydrodynamic Experiments in NaK Karlsruhe
MEKKA
water model of ASTRID hot pool
MICAS
molybdenum
Mo
mixed oxide
MOX
molten salt reactor
MSR
Multi-purpose hYbrid Research Reactor for High-tech Applications
MYRRHA