Page 23 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

xxii Nomenclature

MYRRHABelle MYRRHA Basic sEt-up for Liquid Flow Experiments
MYRRHA Research and Transmutation Endeavour
MYRTE
sodium
Na
sodium potassium
NaK
NAtural CIrculation Experiment
NACIE
natural convection loop
NCL
nondimensional number
NDN
Nuclear Energy Agency
NEA
water model of EFR
NEPTUN
neodymium
Nd
nickel
Ni
net positive suction head
NPSH
Nusselt number
Nu
Organization for Economic Cooperation and Development
OECD
Purdue Advanced Reactor Core Simulator
PARCS
lead
Pb
lead bismuth
PbBi
lead oxide
PbO
predictive capability maturity model
PCCM
probability density function
PDF
Peclet number
Pe
Prova Elementi Combustibile (Italian)
PEC
Prototype Fast Breeder Reactor
PFBR
prototype fast reactor
PFR
proportional integral derivative
PID
process identification and ranking table
PIRT
particle image velocimetry
PIV
PLAnt for Cleaning of large Equipment
PLACE
plant dynamics test loop
PLANDTL
programmable logic controller
PLC
poly(methyl methacrylate)
PMMA
Prandtl number
Pr
Pr t turbulent Prandtl number
power spectral density
PSD
particle tracking velocimetry
PTV
pressurized water reactor
PWR
quasi-DNS
QDNS
research and development
R&D
water model of EFR
RAMONA
Reynold-averaged Navier-Stokes
RANS
Rayleigh-Benard convection
RBC
Reynolds number
Re
Reactor Excursion and Leak Analysis Program
RELAP
Richardson number
Ri
refractive index matching
RIM
Reynolds stress model
RSM
reactor vessel auxiliary cooling system
RVACS
regularized variational multiscale
RVMS
solid to fluid
S2F