Page 24 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Nomenclature xxiii

ScAled Model of Reactor Assembly for Thermal hydraulic studies
SAMRAT
subchannel thermal hydraulics
SCTH
Swedish Advanced Lead-cooled Reactor
SEALER
Safe ExploitAtion Related CHemistry for HLM reactors
SEARCH
Southwest Experimental Fast Oxide Reactor
SEFOR
thermal hydraulic simulations and experiments for the safety assessment of
SESAME
metal-cooled reactors
separate effect test
SET
sodium-cooled fast reactor
SFR
simple gradient diffusion hypothesis
SGDH
sub-grid scale
SGS
steam generator tube rupture
SGTR
Sustainable Nuclear Energy Technology Platform
SNE-TP
Schneller Natriumgek€ uhlter Reaktor (German)
SNR
SOdium Loop for TEst materials and Corrosion facilities
SOLTEC
Sophisticated Plant Evaluation Code for Thermal-hydraulic Response
SPECTRA
Assessment
system response quantity
SRQ
shear stress transport
SST
Strouhal number
St
system thermal hydraulics
STH
Svintsovo-Vismutovyi Bystryi Reaktor (Russian)
SVBR
tantalum
Ta
thermocouple
TC
transient eddy-current flow meter
TEC-FM
Test Loop for Lead Material testing
TELEMAT
Thermal-hydraulics and ADS Design
THEADES
Technology for Heavy Liquid Metals Systems
THESYS
Thermal Hydraulics of Innovative Nuclear Systems
THINS
turbulence model for buoyant flows
TMBF
ultrasound Doppler velocimetry
UDV
unprotected loss of flow
ULOF
uninterruptible power supply
UPS
uncertainty quantification
UQ
unsteady RANS
URANS
The United States
US
ultrasound transit-time technique
UTTT
Virtual European Lead LAboratory
VELLA
volume of fluid
VOF
variational multiScale
VMS
verification and validation
V&V
verification, validation and uncertainty quantification
VVUQ
tungsten
W
wall-adapting local eddy viscosity
WALE
xenon
Xe
yttrium aluminum garnet
YAG
yttrium lithium fluoride
YLF