8. Block Parameters

This document lists all of the Block Parameters that are provided by the ARMI Framework and included plugins.

Block Parameters from Framework

Name	Description	Units
orientation	Triple representing rotations counterclockwise around each spatial axis. For example, a hex assembly rotated by 1/6th has orientation (0,0,60.0)	degrees
pinLocation	Location of fuel pins	None
detailedNDens	High-fidelity number density vector with up to thousands of nuclides. Used in high-fi depletion runs where low-fi depletion may also be occurring. This param keeps the hi-fi and low-fi depletion values from interfering. See core.p.detailedNucKeys for keys.	atoms/bn-cm
burnupMWdPerKg	Burnup in MWd/kg of initial heavy metal	MWd/kg
fissileFraction	Ratio of fissile mass to heavy metal mass at block-level	None
molesHmBOL	Total number of atoms of heavy metal at BOL assuming a full assembly	mole
massHmBOL	Mass of heavy metal at BOL	grams
molesHmBOLByPin	Total number of atoms of heavy metal at BOL	mole
molesHmNow	Total number of atoms of heavy metal	mole
newDPA	Dose in DPA accrued during the current time step	dpa
percentBu	Percentage of the initial heavy metal atoms that have been fissioned	%FIMA
percentBuByPin	Percent burnup of the initial heavy metal atoms that have been fissioned for each pin	%FIMA
percentBuMax	Maximum percentage in a single pin of the initial heavy metal atoms that have been fissioned	%FIMA
percentBuMaxPinLocation	Peak burnup pin location	int
percentBuMin	Minimum percentage of the initial heavy metal atoms that have been fissioned	%FIMA
residence	Duration that a block has been in the core at full power.	EFP days
depletionMatrix	Full BurnMatrix objects containing transmutation and decay info about this block.	N/A
cycleAverageBurnMatrix	Integrated burn matrix mapping this block from its BOC to EOC number densities.	N/A
bu	?
buGroup	The burnup group letter of this block	N/A
buGroupNum	An integer representation of the burnup group, linked to buGroup.	N/A
buRate	Current rate of burnup accumulation. Useful for estimating times when burnup limits may be exceeded.	%FIMA/day
detailedDpa	displacements per atom	dpa
detailedDpaPeak	displacements per atom with peaking factor	dpa
detailedDpaRate	Current time derivative of average detailed DPA	dpa/s
displacementX	Assembly displacement in the x direction	m
displacementY	Assembly displacement in the y direction	m
powerRx	?	W/cm$^3$
dpaRx	?	dpa/s
heliumInB4C	?	He/s/cm$^3$
timeToLimit	Time unit block violates its burnup limit.	days
zbottom	Axial position of the bottom of this block	cm
ztop	Axial position of the top of this block	cm
baseBu	?	?
basePBu	?	?
hydDiam	?	?
nHMAtBOL	Ndens of heavy metal at BOL	atoms/bn-cm.
z	Center axial dimension of this block	cm
pinPeakingStdDev	Standard deviation of the pin peaking factors for the block	None
topIndex	the axial block index within its parent assembly (0 is bottom block)
eqRegion	Equilibrium shuffling region. Corresponds to how many full cycles fuel here has gone through.
eqCascade	Cascade number in repetitive equilibrium shuffling fuel management.
id	?	?
height	the block height	cm
xsType	The xs group letter of this block	N/A
xsTypeNum	An integer representation of the cross section type, linked to xsType.	N/A
type	string name of the input block	N/A
regName	Set by Assembly in writeNIP30 once the region has been placed	?
VoideddopplerWorth	Distributed Voided Doppler constant.	dk/kk’ K**(n-1)
dopplerWorth	Distributed Doppler constant.	dk/kk’ * K^(n-1)
distortWorth	Distortion reactivity distribution	pcm/cm^3
fuelWorth	Reactivity worth of fuel material per unit mass	dk/kk’-kg
fuelWorthDollarsPerKg	Reactivity worth of fuel material per unit mass	$/kg
fuelWorthPT	Fuel reactivity	pcm/%/cm^3
structWorthPT	Structure reactivity	pcm/%/cm^3
radExpWorthPT	Radial swelling reactivity	pcm/%/cm^3
coolWorthPT	Coolant reactivity	pcm/%/cm^3
coolFlowingWorthPT	Flowing coolant reactivity	pcm/%/cm^3
axExpWorthPT	Axial swelling reactivity	pcm/%/cm^3
coolantWorth	Reactivity worth of coolant material per unit mass	dk/kk’-kg
coolantWorthDollarsPerKg	Reactivity worth of coolant material per unit mass	$/kg
cladWorth	Reactivity worth of clad material per unit mass	dk/kk’-kg
cladWorthDollarsPerKg	Reactivity worth of clad material per unit mass	$/kg
structureWorth	Reactivity worth of structure material per unit mass	dk/kk’-kg
structureWorthDollarsPerKg	Reactivity worth of structure material (non-clad and non-wire wrap material) per unit mass	$/kg
rxAxialCentsPerK	Axial temperature reactivity coefficient	cents/K
rxAxialCentsPerPow	Axial power reactivity coefficient	cents/K
rxCoolantCentsPerK	Coolant temperature reactivity coefficient	cents/K
rxCoolantCentsPerPow	Coolant power reactivity coefficient	cents/K
rxDopplerCentsPerK	Doppler temperature reactivity coefficient	cents/K
rxDopplerCentsPerPow	Doppler power reactivity coefficient	cents/K
rxFuelCentsPerK	Fuel temperature reactivity coefficient	cents/K
rxFuelCentsPerPow	Fuel power reactivity coefficient	cents/K
rxNetCentsPerK	Net temperature reactivity coefficient	cents/K
rxNetCentsPerPow	Net power reactivity coefficient	cents/K
rxNetPosNeg	Net temperature reactivity coefficient: positive or negative	cents/K
rxNetPosNegPow	Net power reactivity coefficient: positive or negative	cents/K
rxRadialCentsPerK	Radial temperature reactivity coefficient	cents/K
rxRadialCentsPerPow	Radial power reactivity coefficient	cents/K
rxStructCentsPerK	Structure temperature reactivity coefficient	cents/K
rxStructCentsPerPow	Structure power reactivity coefficient	cents/K
rxVoidedDopplerCentsPerK	Voided Doppler temperature reactivity coefficient	cents/K
rxVoidedDopplerCentsPerPow	Voided Doppler power reactivity coefficient	cents/K
virdentGr	Radial surface leakage reactivity	pcm/%/cm^3
virdentGz	Axial surface leakage reactivity	pcm/%/cm^3
virdentLr	Radial volume leakage reactivity	pcm/%/cm^3
virdentLz	Axial volume leakage reactivity	pcm/%/cm^3
assemPeakStd	Spectral reactivity	pcm/%/cm^3
virdentS	Spectral reactivity	pcm/%/cm^3
rxFuelDensityCoeffPerMass	Fuel Density Coefficient	dk/kk’-kg
rxFuelDopplerConstant	Fuel Doppler Constant	dk/kk’ K**(n-1)
rxFuelVoidedDopplerConstant	Fuel Voided-Coolant Constant	dk/kk’ K**(n-1)
rxFuelTemperatureCoeffPerMass	Fuel Temperature Coefficient	dk/kk’-kg
rxFuelVoidedTemperatureCoeffPerMass	Fuel Voided-Coolant Temperature Coefficient	dk/kk’-kg
rxCladDensityCoeffPerMass	Clad Density Coefficient	dk/kk’-kg
rxCladDopplerConstant	Clad Doppler Constant	dk/kk’ K**(n-1)
rxCladTemperatureCoeffPerMass	Clad Temperature Coefficient	dk/kk’-kg
rxStructureDensityCoeffPerMass	Structure Density Coefficient	dk/kk’-kg
rxStructureDopplerConstant	Structure Doppler Constant	dk/kk’ K**(n-1)
rxStructureTemperatureCoeffPerMass	Structure Temperature Coefficient	dk/kk’-kg
rxCoolantDensityCoeffPerMass	Coolant Density Coefficient	dk/kk’-kg
rxCoolantTemperatureCoeffPerMass	Coolant Temperature Coefficient	dk/kk’-kg
rxFuelDensityCoeffPerTemp	Fuel Density Coefficient	dk/kk’-K
rxFuelDopplerCoeffPerTemp	Fuel Doppler Coefficient	dk/kk’-K
rxFuelVoidedDopplerCoeffPerTemp	Fuel Voided-Coolant Doppler Coefficient	dk/kk’-K
rxFuelTemperatureCoeffPerTemp	Fuel Temperature Coefficient	dk/kk’-K
rxFuelVoidedTemperatureCoeffPerTemp	Fuel Voided-Coolant Temperature Coefficient	dk/kk’-K
rxCladDensityCoeffPerTemp	Clad Density Coefficient	dk/kk’-K
rxCladDopplerCoeffPerTemp	Clad Doppler Coefficient	dk/kk’-K
rxCladTemperatureCoeffPerTemp	Clad Temperature Coefficient	dk/kk’-K
rxStructureDensityCoeffPerTemp	Structure Density Coefficient	dk/kk’-K
rxStructureDopplerCoeffPerTemp	Structure Doppler Coefficient	dk/kk’-K
rxStructureTemperatureCoeffPerTemp	Structure Temperature Coefficient	dk/kk’-K
rxCoolantDensityCoeffPerTemp	Coolant Density Coefficient	dk/kk’-K
rxCoolantTemperatureCoeffPerTemp	Coolant Temperature Coefficient	dk/kk’-K
VirDenTerr	VirDenT error	%
assemNum	Index that refers, nominally, to the assemNum parameter of the containing Assembly object. This is stored on the Block to aid in visualizing shuffle patterns and the like, and should not be used within the code. These are not guaranteed to be consistent with the containing Assembly, so they should not be used as a reliable means to reconstruct the model.	None
avgFuelTemp	?	?
avgTempRef	?	?
axExtenNodeHeight	Axial extension node height	meter
blockBeta	Beta in each block	unitless
blockF	Adjoint-weighted fission source in each block	1/cm^5/s^2
bondBOL	?	?
breedRatio	Breeding ratio	None
fissileDestroyed	Fissile atoms destroyed in last depletion step (not net!)	atoms/bn-cm
fissileBefore	Fissile atoms at beginning of last depletion step (could be substep!)	atoms/bn-cm
fissileAfter	Fissile atoms at end of last depletion step (could be substep!)	atoms/bn-cm
buLimit	Burnup limit	%FIMA
cladACCI	The amount of cladding wastage due to absorber chemical clad interaction	µm
convRatio	Conversion ratio	None
coolRemFrac	Fractional sodium density change for each block	?
crWastage	Combines ACCI and clad corrosion for control blocks	µm
cyclicNErr	Relative error of the block number density	None
deltaTclad	Change in fuel temperature due to 1% rise in power.	1/cm^5/s^2
deltaTduct	Change in fuel temperature due to 1% rise in power.	1/cm^5/s^2
deltaTfuel	Change in fuel temperature due to 1% rise in power.	1/cm^5/s^2
dilationElasticPM	Combined elastic membrane and bending components of duct dilation	mm
dilationElasticT	Thermal expansion component of duct dilation	mm
dilationElasticTRefueling	Thermal expansion component of duct dilation at refueling temperature (180C)	mm
dilationCreepIrrad	Irradiation creep component of duct dilation	mm
dilationSwellingSF	Stress-free void swelling component of duct dilation	mm
blockAxialSwellingSF	Axial stress-free void swelling of block	mm
dilationSwellingSE	Stress-enhanced swelling component of duct dilation	mm
dilationCreepTh1	Primary thermal creep component of duct dilation	mm
dilationCreepTh2	Secondary thermal creep component of duct dilation	mm
dilationTotal	Total duct dilation	mm
dilationRefueling	Amount of duct dilation at refueling temperature (180C)	mm
displacementMAG	?	?
heightBOL	As-fabricated height of this block (as input). Used in fuel performance. Should be constant.	cm
intrinsicSource	Intrinsic neutron source from spontaneous fissions before a decay period	?
intrinsicSourceDecayed	Intrinsic source from spontaneous fissions after a decay period	?
kgFis	Mass of fissile material in block	kg
kgHM	Mass of heavy metal in block	kg
mchan	SASSYS/DIF3D-K (external) channel index assignment	None
mreg	SASSYS/DIF3D-K radial region index assignment	None
nPins	Number of pins	None
newDPAPeak	The peak DPA accumulated in the last burn step	dpa
percentBuPeak	Peak percentage of the initial heavy metal atoms that have been fissioned	%FIMA
powerShapeDelta	Change in power shape when core temperature rises.	W
powerShapePercent	Percent change in power shape when core temperature rises.	%
puFrac	Current Pu number density relative to HM at BOL	None
smearDensity	Smear density of fuel pins in this block. Defined as the ratio of fuel area to total space inside cladding.	?
distortionReactivity	?	?
harmonic	?	?
harmonicAdj	?	?

Block Parameters from NeutronicsPlugin

Name	Description	Units
axMesh	number of neutronics axial mesh points in this block
mgFlux	multigroup volume-integrated flux	n-cm/s
adjMgFlux	multigroup adjoint neutron flux	n-cm/s
lastMgFlux	multigroup volume-integrated flux used for averaging the latest and previous depletion step	n-cm/s
mgFluxGamma	multigroup gamma flux	g-cm/s
mgNeutronVelocity	multigroup neutron velocity	cm/s
extSrc	multigroup external source	g/cm^3/s
mgGammaSrc	multigroup gamma source	g/cm^3/s
gammaSrc	gamma source	g/cm^3/s
mgFluxSK	multigroup volume-integrated flux stored for multiple time steps in spatial kinetics (2-D array)
pinMgFluxes	The block-level pin multigroup fluxes. pinMgFluxes[g][i] represents the flux in group g for pin i. Flux units are the standard n/cm^2/s. The “ARMI pin ordering” is used, which is counter-clockwise from 3 o’clock. See TP1-1.9.31-RPT-0010 for more details.	n/s/cm$^2$
pinMgFluxesAdj	should be a blank 3-D array, but re-defined later (ng x nPins x nAxialSegments)
pinMgFluxesGamma	should be a blank 3-D array, but re-defined later (ng x nPins x nAxialSegments)	g/s/cm$^2$
pinPowers	The block-level pin linear power densities. pinPowers[i] represents the average linear power density of pin i. Power units are Watts/cm (Watts produced per cm of pin length). The “ARMI pin ordering” is used, which is counter-clockwise from 3 o’clock. See TP1-1.9.31-RPT-0010 for more details.	W/cm
pinPowersNeutron	The block-level pin linear power densities from neutron-induced interactions. pinPowersNeutron[i] represents the average linear power density of pin i (from neutron heating). Power units are Watts/cm (Watts produced per cm of pin length).	W/cm
pinPowersGamma	The block-level pin linear power densities from gamma heating. pinPowersGamma[i] represents the average linear power density of pin i (from gamma heating). Power units are Watts/cm (Watts produced per cm of pin length).”,	W/cm
axialPowerProfile	For each reconstructed axial location, a tuple (z,power density) where with axial origin at the bottom of assembly in which the blocks are located.
axialPowerProfileNeutron
axialPowerProfileGamma
axialMgFluxReconCoeff	The coefficients in the axial multigroup flux profile polynomial for this block. The flux profile is usually A*z^4 + B*z^3 + C*z^2 + D*z + E, and so this variable will be the 5 x ng list, so axialMgFluxReconCoeff[g][i] is the ith coefficient for flux group g. Also, this flux profile is normalized (for each group) so that its average is always 1.0 in each block. One must multiply the coefficients of each group by the block-average group flux to obtain the axial group flux profile.
axialMgFluxProfileAdj
axialMgFluxProfileNeutron
axialMgFluxProfileNeutronAdj
axialMgFluxProfileGamma
radialMgFluxProfile
radialMgFluxProfileAdj
radialMgFluxProfileNeutron
radialMgFluxProfileNeutronAdj
radialMgFluxProfileGamma
betad	Delayed neutron beta
chi	Energy distribution of fission neutrons
chid	Energy distribution of delayed fission neutrons
linPow	Pin-averaged linear heat generation rate	W/m
linPowByPin	Pin linear power	W/cm
linPowByPinNeutron	Pin linear neutron power	W/cm
linPowByPinGamma	Pin linear gamma power	W/cm
reactionRates	List of reaction rates in specified by setting “reactionsToDB”	Reactions/sec
rateBalance	Numerical balance between particle production and destruction (should be small)	1/cm^3/s
rateExtSrc	Rate of production of neutrons from an external source.	1/cm^3/s
rateFisAbs	Neutron abs. rate in fissile material	1/cm^3/s
rateFisSrc	Fission source rate. This is related to production rate in fissile by a factor of keff	1/cm^3/s
rateLeak	Rate that neutrons leak out of this block.	1/cm^3/s
rateParasAbs	Rate of parasitic absorption (absorption in non-fertile/fissionable material)	1/cm^3/s
rateProdNet	Net production rate of neutrons	1/cm^3/s
rateScatIn	Rate neutrons in-scatter in this block	1/cm^3/s
rateScatOut	Rate that neutrons out-scatter in this block (removal - absorption)	1/cm^3/s
capturePowerFrac	Fraction of the power produced through capture in a block.	None
fastFluence	Fast spectrum fluence	#/cm^2
fastFluencePeak	Fast spectrum fluence with a peaking factor	#/cm^2
fluence	Fluence	#/cm^2
flux	neutron flux	n/cm^2/s
fluxAdj	Adjoint flux
fluxAdjPeak	Adjoint flux
pdens	Average volumetric power density	W/cm$^3$
pdensDecay	Decay power density from decaying radionuclides	W/cm$^3$
arealPd	Power divided by XY area	MW/m^2
arealPdGamma	Areal gamma power density	MW/m^2
fertileBonus	The fertile bonus	None
fisDens	Fission density in a pin (scaled up from homogeneous)	fissions/cm^3/s
fisDensHom	Homogenized fissile density	1/cm^3/s
fluxDeltaFromRef	Relative difference between the current flux and the directly-computed perturbed flux.	None
fluxDirect	Flux is computed with a direct method	n/cm^2/s
fluxGamma	Gamma scalar flux	g/cm^2/s
fluxPeak	Peak neutron flux calculated within the mesh	n/cm^2/s
fluxPertDeltaFromDirect	Relative difference between the perturbed flux and the directly-computed perturbed flux	None
fluxPertDeltaFromDirectfluxRefWeighted		None
fluxPerturbed	Flux is computed by MEPT	1/cm^2/s
fluxRef	Reference flux	1/cm^2/s
kInf	Neutron production rate in this block/neutron absorption rate in this block. Not truly kinf but a reasonable approximation of reactivity.	None
medAbsE	Median neutron absorption energy	eV
medFisE	Median energy of neutron causing fission	eV
medFlxE	Median neutron flux energy	eV
pdensGamma	Average volumetric gamma power density	W/cm^3
pdensNeutron	Average volumetric neutron power density	W/cm^3
ppdens	Peak power density	W/cm^3
ppdensGamma	Peak gamma density	W/cm^3
rateAbs	Total absorption rate in this block (fisson + capture).	1/cm^3/s
rateCap	Parasitic capture rate in this block.	1/cm^3/s
rateFis	Fission rate in this block.	1/cm^3/s
rateProdFis	Production rate of neutrons from fission reactions (nu * fission source / k-eff)	1/cm^3/s
rateProdN2n	Production rate of neutrons from n2n reactions.	1/cm^3/s
powerGenerated	Generated power. Different than b.p.power only when gamma transport is activated.	W
power	Total power	W
powerDecay	Total decay power	W
powerGamma	Total gamma power	W
powerNeutron	Total neutron power	W
detailedDpaNewCycle	The total DPA accumulated in all burn steps of one cycle	dpa
detailedDpaPeakNewCycle	The total peak DPA accumulated in all burn steps of one cycle	dpa
detailedDpaThisCycle	Displacement per atom accumulated during this cycle. This accumulates over a cycle and resets to zero at BOC.	dpa
detailedDpaPeakRate	Peak DPA rate based on detailedDpaPeak	DPA/s
dpaPeakFromFluence	DPA approximation based on a fluence conversion factor set in the dpaPerFluence setting	dpa
enrichmentBOL	Enrichment during fabrication	mass fraction
fastFlux	Neutron flux above 100keV	1/cm^2/s
fastFluxFr	Fraction of flux above 100keV
cornerFastFlux	Neutron flux above 100keV at hexagon block corners	n/cm^2/s
pointsFastFluxFr	Fraction of flux above 100keV at points within the block	None
pointsDpa	displacements per atom at points within the block	dpa
pointsDpaRate	Current time derivative of the displacement per atoms at points within the block	dpa/s
pdensGenerated	Volume-averaged generated power density. Different than b.p.pdens only when gamma transport is activated.	W/cm^3

Block Parameters from FuelPerformancePlugin

Name	Description	Units
gasReleaseFraction	Fraction of generated fission gas that no longer exists in the block. Should be between 0 and 1, inclusive.	fraction
bondRemoved	Fraction of thermal bond between fuel and clad that has been pushed out. Should be between 0 and 1, inclusive.	fraction
cladWastage	Total cladding wastage from inner and outer surfaces.	µm
totalCladStrain	Total diametral clad strain.	%
axialGrowthPct	Axial growth percentage	%
fpPeakFuelTemp	Fuel performance calculated peak fuel temperature.	C
fpAveFuelTemp	Fuel performance calculated average fuel temperature.	C
gasPorosity	Fraction of fuel volume that is occupied by gas pores
liquidPorosity	Fraction of fuel volume that is occupied by liquid filled pores
fuelRadialDisplacement	Radial fuel displacement from irradiation	cm

Block Parameters from ThermalHydraulicsPlugin

Name	Description	Units
pressureLossCoeffs	Pressure loss coefficients from form losses outside of bundle region of assembly, e.g. losses through pin attachment hardware, expansion in inlet nozzle.
inletLossCoeff	Pressure loss coefficients from form losses to be applied at the block inlet
THaveInletVel	Average fluid velocity taken at the inlet of the block.	m/s
THaveOutletVel	Average fluid velocity taken at the outlet of the block.	m/s
THdeltaPAccel	Acceleration component to the pressure drop.	Pa
THdeltaPFric	Friction component to the pressure drop.	Pa
THdeltaPInlet	Pressure drop at the inlet of the block.	Pa
THdeltaPOutlet	Pressure drop at the outlet of the block.	Pa
THhotChannelCladMidwallT	Midwall (average) clad temperature for the hot channel or hot pin.	°C
THhotChannelHeatTransferCoeff	Film heat transfer coefficient for hot channel in the assembly.	W/m^2/K
THinletDynamicPressure	Dynamic pressure drop component taken at the inlet of the block.	Pa
THmixingLength	Approximation of length for subchannel mixing in subchan model.
THpeakingStdDev	Standard deviation of pin peaking for modeling pin-level power in subchan.
THradialPeakingFactor	Approximation of radial peaking for modeling pin-level power in subchan.
THhotChannelCladODT	Nominal clad outer diameter temperature of the hot pin	°C
THhotChannelCladIDT	Nominal clad inner diameter temperature of the hot pin	°C
THhotChannelFuelODT	Temperature of the fuel outer diameter	°C
THhotChannelFuelCenterlineT	Nominal hot channel fuel centerline temperature	°C
THdeltaPBundle	Pressure difference in a bundle, including contributions from friction, acceleration, and gravity	Pa
TH0SigmaCladODT	0-sigma clad outer diameter temperature of the hot pin	°C
TH2SigmaCladODT	2-sigma clad outer diameter temperature of the hot pin	°C
TH3SigmaCladODT	3-sigma clad outer diameter temperature of the hot pin	°C
TH0SigmaCladIDT	0-sigma clad inner diameter temperature of the hot pin	°C
TH2SigmaCladIDT	2-sigma clad inner diameter temperature of the hot pin	°C
TH3SigmaCladIDT	3-sigma clad inner diameter temperature of the hot pin	°C
TH0SigmaFuelCenterlineT	0-sigma fuel centerline temperature	°C
TH2SigmaFuelCenterlineT	2-sigma fuel centerline temperature	°C
TH3SigmaFuelCenterlineT	3-sigma fuel centerline temperature	°C
THdilationPressure	Dilation pressure	Pa
THmaxLifeTimePower	Maximum power over the lifetime of this block.	W
TH0SigmaOutletT	0-sigma clad outer diameter temperature of the hot pin	°C
TH2SigmaOutletT	2-sigma clad outer diameter temperature of the hot pin	°C
TH3SigmaOutletT	3-sigma clad outer diameter temperature of the hot pin	°C
THTfuelCL	Average temperature of the fuel centerline used for neutronic coupling	°C
THTfuelOD	Average temperature of the fuel outer diameter used for neutronic coupling	°C
THaverageCladODT	Block average of the outer clad temperature.	°C
THaverageCladIDT	Block average of the inner clad temperature	°C
THassemPressDrop	The pressure drop across this block	Pa
THaveCoolantVel	Average of the inlet and outlet coolant velocities	m/s
THaverageCladTemp	The nominal average clad temperature in the block, which should be used for neutronic and TH feedback.	°C
THaverageGapTemp	The nominal average gap temperature in the block, which should be used for neutronic and TH feedback.	°C
THaverageDuctTemp	The nominal average duct temperature in the block, which should be used for neutronic and TH feedback.	°C
THcoolantAverageT	Flow-based average of the inlet and outlet coolant temperatures.	°C
THcoolantInletT	The nominal average bulk coolant inlet temperature into the block.	°C
THcoolantOutletT	Coolant temperature at the outlet of this block	°C
THcoolantStaticT	Volume-based average coolant temperature, recommended for neutronics	°C
THdPfrict	Frictional pressure drop	Pa
THdeltaPFormLoss	Pressure differences due to user input loss coefficeints	Pa
THdeltaPGrav	hydrostatic pressure difference in a block	Pa
THdeltaPNoGrav	Sum of the loss pressure drops due to friction, acceleration, and inlet + outlet	Pa
THdeltaPTotal	Total pressure difference in a block	Pa
THinletCoolantVel	Flow velocity	m/s
THhotChannelOutletT	Nominal hot channel outlet temperature	°C
THlocalDTout	Maximum delta-Ts for outlet temperatures of all assemblies	°C
THlocalDToutFuel	Maximum delta-Ts for outlet temperatures of fuel assemblies	°C
THmassFlowRate	Mass flow rate	kg/s
THmaxCoolantVel	The maximum outlet coolant velocity	m/s
THorificeSetting	A list of orifice settings corresponding to the assembly list	Pa/(kg/s)**2
THorificeZone	A list of orificing zones corresponding to the assembly list
THcornTemp	Best estimate duct temperature [degC] for assembly corners	°C
THedgeTemp	Best estimate duct temperature for assembly edges	°C
THbundleAveTemp	Bundle averaged temperature	°C
THcoldChanTemp	Best estimate cold channel temperature	°C
THcoldChannel	Cold channel (lowest coolant dT) identifier
THcoldPin	Cold pin (lowest PCT) pin identifier
THhotChannel	Hot channel (highest coolant dT) identifier
THhotPin	Hot pin (highest PCT) pin identifier