Page 20 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Nomenclature

above core barrel
ACB
ADvanced Reactor Initiative and Network Arrangement
ADRIANA
accelerator-driven system
ADS
silver
Ag
algebraic heat flux model
AHFM
analytic hierarchy process
AHP
aluminum
Al
Advanced Lead Fast Reactor European Demonstrator
ALFRED
Karlsruhe experiments with Li and Na free jet
ALINA
annular linear induction pump
ALIP
anisotropic porosity
AP
assessment of computational fluid dynamics codes for heavy liquid metals
ASCHLIM
Advanced Sodium Technological Reactor for Industrial Demonstration
ASTRID
Analysis of THermal hydraulics of LEaks and Transients
ATHLET
boundary condition
BC
backward-facing step
BFS
Bystrie Neytrony (Russian for fast neutron)
BN
beginning of life
BOL
Bystrij Opytnyj Reaktor (Russian)
BOR
best practice guidelines
BPG
Bystrie Reaktor (Russian)
BR
Russian lead-cooled fast reactor design
BREST
boiling water reactor
BWR
computer-aided design
CAD
code for analysis of thermal-hydraulics during an accident of reactor and
CATHARE
safety evaluation
charged-coupled device
CCD
core disruptive accident
CDA
cumulative density function
CDF
central design team
CDT
Chinese experimental fast reactor
CEFR
computational fluid dynamics
CFD
Courant-Friedrichs-Lewy
CFL
coarse-grid-CFD
CGCFD
CHEmistry and OPErations
CHEOPE
contactless inductive flow tomography
CIFT
CIRColazione Eutettico (Italian)
CIRCE
China LEAd-based research reactor
CLEAR