3.5. Settings Report

This document lists all the settings in ARMI.

They are all accessible to developers through the armi.settings.caseSettings.Settings object, which is typically stored in a variable named cs. Interfaces have access to a simulation’s settings through self.cs.

ARMI Settings

Name	Description	Default	Units
DPAXSDirectoryPath	DPA XS Directory Path	\\albert\apps\dev\mc2\3.2 .2\libraries\endfb- vii.0\damage_xs
HCFcoretype	Switch to apply different sets of hot channel factors based on design being analyzed	TWRC
Tin	The inlet temperature of the reactor in C	360.0
Tout	The outlet temperature of the reactor in C	510.0
acceptableBlockAreaError	This is the limit of error in between the block’s cross sectional area and the reference block used during the assembly area consistency check	1e-05
assemPowSummary	Print out a summary of how much power is in each assembly type at every timenode.
assemblyRotationAlgorithm	The algorithm to use to rotate the detail assemblies while shuffling
assemblyRotationStationar y	Whether or not to rotate assemblies that are not shuffled.This can only be True if ‘rotation’ is true.
automaticVariableMesh	This is a flag to let armi add additional mesh points if the dif3d mesh is too irregular
availabilityFactor	Availability factor of the plant. This is the fraction of the time that the plant is operating. If variable, use availabilityFactors setting.	1.0
availabilityFactors	List of availability factor of each cycle as a fraction (fraction of time plant is not in an outage). R is repeat. For example [0.5, 1.0, ‘9R’] is 1 50% CF followed by 10 100 CF. Empty list is constant duration set by ‘availabilityFactor’.
axialDollarssPerK	Compute axial reactivity coefficients in $/K instead of $/kg. useful for RELAP.
axialExpPT	Compute the core-wide fuel axial expansion reactivity coefficient with perturbation theory.
axialMeshRefinementFactor	Multiplicative factor on the Global Flux number of mesh per block. Used for axial mesh refinement.	1
bcCoefficient	Value for the parameter A of the DIF3D generalized boundary condition.
beta	Effective delayed neutron fraction. You may need to enter the precursor groups in detail elsewhere to do kinetics.
betaComponents	Manually set individual precursor group delayed neutron fractions
blockParameterNamesToIgno reOnDBLoading	Block parameter data (names) to exclude when loading from the database
blockParameterNamesToIncl udeOnDBLoading	Block parameter data (names) to load from the database
blockTypesToIgnoreOnDBLoa ding	Block types to exclude when loading the database
boundaries	External Neutronic Boundary Conditions. Reflective does not include axial.	Extrapolated
branchVerbosity	Verbosity of the non- master MPI nodes	error
buGroups	The range of burnups where cross-sections will be the same for a given assembly type	[10, 20, 30, 100]
burnChainFileName	Path to YAML file that has the depletion chain defined in it	C:\users\ntouran\codes\ar mi\framework\armi\resourc es\burn-chain.yaml
burnSteps	Number of depletion substeps in one cycle, n. Note: There will be n+1 time nodes so the burnup step time will be computed as cycle length/n+1.	4
burnupPeakingFactor	None
circularRingMode	Toggle between circular ring definitions to hexagonal ring definitions
circularRingOrder	Order by which locations are sorted in circular rings for equilibrium shuffling	angle
circularRingPitch	The relative pitch to be used to define a single circular ring in circular shuffling.	1.0
clearXS	Delete all cross section libraries before regenerating them.
comment	A comment describing this case.
conditionalModuleName	This is file name – directory not included – of the python module that contains a conditional function to determine the end of burn cycles
copyFilesFrom	None
copyFilesTo	None
coverage	Turn on coverage report generation which tracks all the lines of code that execute during a run
createAssemblyTypeZones	Let ARMI create zones based on fuel type automatically
crossSectionControl	Data structure defining how cross sections are created
customFuelManagementIndex	An index that determines which of various options is used in management. Useful for optimization sweeps.
cycleLength	Duration of one single cycle. If availability factor is below 1, the reactor will be at power less than this. If variable, use cycleLengths setting.	365.242199
cycleLengths	List of durations of each cycle in days. The at- power duration will be affected by the availability factor. R is repeat. For example [100, 150, ‘9R’] is 1 100 day cycle followed by 10 150 day cycles. Empty list is constant duration set by ‘cycleLength’.
db	Write the state information to a database at every timestep.	True
dbStorageAfterCycle	Only store cycles after this cycle in the DB (to save storage space)
debug	None
debugDB	debugDB
debugMem	Turn on memory debugging options to help find problems with the code
debugMemSize	Show size of objects during memory debugging
decayConstants	Manually set individual precursor group delayed neutron decay constants
defaultSnapshots	Generate snapshots at BOL, MOL, and EOL.
deferredInterfaceNames	Interfaces to delay the normal operations of for special circumstance problem avoidance
deferredInterfacesCycle	The supplied list of interface names in deferredInterfaceNames will begin normal operations on this cycle number.
detailAllAssems	All assemblies will have ‘detailed’ treatment. Note: This option is interpreted differently by different modules.
detailAssemLocationsBOL	Assembly locations for assemblies that will have ‘detailed’ treatment. This option will track assemblies in the core at BOL. Note: This option is interpreted differently by different modules.
detailAssemNums	Assembly numbers(IDs) for assemblies that will have ‘detailed’ treatment. This option will track assemblies that not in the core at BOL. Note: This option is interpreted differently by different modules.
detailedAxialExpansion	Allow each assembly to expand independently of the others. Results in non-uniform axial mesh. Neutronics kernel must be able to handle.
disableBlockTypeExclusion InXsGeneration	Use all blocks in a cross section group when generating a representative block. When this is disabled only fuel blocks will be considered
doOrificedTH	Perform orificed thermal hydraulics (requires bounds file from a previous case).
dpaPerFluence	A quick and dirty conversion that is used to get dpaPeak by multiplying the factor and fastFluencePeak	4.01568627451e-22
dumpLocationSnapshot	Assembly locations and snapshots to dump detailed assembly data.
dumpSnapshot	List of snapshots to dump detailed reactor analysis data. Can be used to perform follow-on analysis (i.e., Reactivity coefficient generation).
eigenProb	Whether this is a eigenvalue problem or a fixed source problem	True
epsEig	convergence criterion for calculating the eigenvalue	1e-07
epsFSAvg	Convergence criteria for average fission source	1e-05
epsFSPoint	Convergence criteria for point fission source	1e-05
eqDirect	Does the equilibrium search with repetitive shuffing but with direct shuffling rather than the fast way.
existingFixedSource	Specify an exiting fixed source input file.
explicitRepeatShuffles	Path to file that contains a detailed shuffling history that is to be repeated exactly.
fluxRecon	Perform detailed flux and power reconstruction
fpModel	The fission product model to use in this ARMI run	infinitelyDilute
freshFeedType	None	feed fuel
fuelHandlerName	None
genReports	Employ the use of the reporting utility for ARMI, generating HTML and ASCII summaries of the run	True
genXS	Generate multigroup cross sections for the selected particle type(s) using the specified lattice physics kernel (see Lattice Physics tab).
geomFile	Input file containing BOL core map.
globalFluxActive	Calculate the global flux at each timestep for the selected particle type(s) using the specified neutronics kernel (see Global Flux tab).	Neutron
groupStructure	Energy group structure to use in neutronics simulations	ANL33
growToFullCoreAfterLoad	Grows from 1/3 to full core after loading from a 1/3 symmetric snapshot. Note: This is needed when a full core model is needed and the database was produced using a third core model
hexRingGeometryConversion	Convert the core geometry model to RZ/RZT using hexagonal ring zones. Note: If this is disabled, circular ring zones will be used.
independentVariables	List of (independentVarName, value) tuples to inform optimization post- processing.
infiniteDiluteCutoff	Do not model nuclides with density less than this cutoff. Used with PARTISN and SERPENT.	1e-10
jumpRingNum	None	8
levelsPerCascade	None	14
lfpCompositionFilePath	Path to the file that contains lumped fission product composition definitions (e.g. equilibrium yields)
loadFromDBEveryNode	Every node loaded from reference database
loadPadElevation	The elevation of the bottom of the above-core load pad (ACLP) in cm from the bottom of the upper grid plate. Used for calculating the load pad dose
loadPadLength	The length of the load pad. Used to compute average and peak dose.
loadStyle	Description of how the ARMI case will be initialized	fromInput
loadingFile	Browse for the blueprints/loading input file containing component dimensions, materials, etc.
looseCoupling	Update material densities and dimensions after running thermal- hydraulics. Note: Thermal-hydraulics calculation is needed to perform the loose physics coupling calculation.
lowPowerRegionFraction	Description Needed	0.05
makeAllBlockLFPsIndepende nt	Flag to make all blocks have independent lumped fission products
materialNamespaceOrder	Ordered list of Python namespaces for finding materials by class name. This allows users to choose between different implementations of reactor materials. For example, the framework comes with a basic UZr material, but power users will want to override it with their own UZr subclass. This allows users to specify to get materials out of a plugin rather than from the framework.
memPerNode	Memory requested per cluster node	2000
minMeshSizeRatio	This is the minimum ratio of mesh sizes (dP1/(dP1 + dP2)) allowable – only active if automaticVariableMesh flag is set to True	0.15
minimumFissileFraction	Minimum fissile fraction (fissile number densities / heavy metal number densities).	0.045
minimumNuclideDensity	Density to use for nuclides and fission products at infinite dilution. This is also used as the minimum density.	1e-15
mpiTasksPerNode	Number of independent processes that are allocated to each cluster node. 0 means 1 process per CPU (or 12 per node on some clusters). Set between 1-12 to increase RAM and number of cores needed for large problems.
nCycles	Number of cycles that will be simulated. Fuel management happens at the beginning of each cycle. Can include active (full- power) cycles as well as post-shutdown decay-heat steps.	1
neutronicsKernel	The neutronics / depletion solver for global flux solve.	DIF3D-Nodal
neutronicsType	The type of neutronics solution that is desired.	real
nuclideHalflifeLibraryPat h	directory path to RIPL data for nuclide levels	\\albert\apps\dev\Nuclear Data\RIPL\halflives\
numControlBlocks	Number of blocks with control for a REBUS poison search	6
numCoupledIterations	Number of tight coupled physics iterations to occur at each timestep.
numProcessors	Number of CPUs to request on the cluster	1
numberMeshPerEdge	Number of mesh per block edge for finite- difference planar mesh refinement.	1
operatorLocation	The path to the operator code to execute for this run (for custom behavior)
outputCacheLocation	Location where cached calculations are stored and retrieved if exactly the same as the calculation requested. Empty string will not cache
outputFileExtension	The default extension for plots	jpg
percentNaReduction	The percent that density will be perturbed in reactivity coefficients	1.0
plotShuffleArrows	Make plots with arrows showing each move.
plots	Generate additional plots throughout the ARMI analysis
power	Nameplate thermal power of the reactor. Can be varied by setting the powerFraction setting.
powerFractions	List of power fractions at each cycle (fraction of rated thermal power the plant achieves). R is repeat. For example [0.5, 1.0, ‘9R’] is 1 50% PF followed by 10 100% PF. Specify zeros to indicate decay-only cycles (i.e. for decay heat analysis). Empty list implies always full rated power.
profile	Turn on the profiler for the submitted case. The profiler results will not include all import times.
radialExpPT	Compute the core-wide radial expansion reactivity coefficient with perturbation theory
reallySmallRun	Clean up files at the beginning of each cycle (BOC)
reloadDBName	Name of the database file to load initial conditions from
removePerCycle	None	3
ringZones	Define zones by concentric radial rings. Each zone will get independent reactivity coefficients.
runLatticePhysicsBeforeSh uffling	Forces the Generation of Cross Sections Prior to Shuffling the Fuel Assemblies. Note: This is recommended when performing equilibrium shuffling branching searches.
runType	Type of run that this is, e.g. a normal run through all cycles, a snapshot loaded rx. coefficient run, etc.	Standard
shuffleLogic	Python script written to handle the fuel shuffling for this case. This is user-defined per run as a dynamic input.
skipCycles	Number of cycles to be skipped during the calculation. Note: This is typically used when repeating only a portion of a calculation or repeating a run.
smallRun	Clean up intermediate files after the run completes (EOL)
splitZones	Automatically split defined zones further based on number of blocks and assembly types.	True
startCycle	Cycle number to continue calculation from. Database will load from the time step just before. For snapshots use dumpSnapshot
startNode	Timenode number (0 for BOC, etc.) to continue calulation from. Database will load from the time step just before.
stationaryBlocks	blocks with these indices (int values) will not move in moves.
structWorthPT	None
summarizeAssemDesign	Printout a summary of the assembly design details at BOL	True
targetK	Target criticality (k-effective) for cycle length, branch, and equilibrium search	1.005
timelineInclusionCutoff	Timers who are not active for this percent of the run will not be presented in the timeline graphic.	0.03
tolerateBurnupChange	Burnup window for computing cross sections. If the prior cross sections were computed within the window, new cross sections will not be generated and the prior calculated cross sections will be used.
trace	Activate Python trace module to print out each line as its executed
trackAssems	track assemblies for detailed fuel histories. Disable in case you get memory errors.	True
updateIndividualAssemblyN umbersOnDbLoad	When a DB is loaded, this will update assembly numbers as well as other state	True
updateMassFractionsFromDB	Update the mass fractions when loading from the database	True
useInputTemperaturesOnDBL oad	when loading from a database, first set all component temperatures to the input temperatures. Required when a coupled TH case is being derived from a case without any coupled TH.
verbosity	How verbose the output will be	info
xsBlockRepresentation	The type of averaging to perform when creating cross sections for a group of blocks	FluxWeightedAverage
xsBucklingConvergence	The convergence criteria for the buckling iteration if it is available in the lattice physics solver	1e-05
xsEigenvalueConvergence	The convergence criteria for the eigenvalue	1e-05
xsKernel	Method to determine broad group cross sections for assemblies	MC2v3
xsScatteringOrder	Scattering order for the lattice physics calculation	3
zeroOutNuclidesNotInDB	If a nuclide was added to the problem after a previous case was run, deactivate this to let it survive in a restart run	True
zoneDefinitions	definitions of zones as lists of assembly locations (e.g. ‘zoneName: loc1, loc2, loc3’) . Zones are groups of assemblies used by various summary and calculation routines
zoneFlowSummary	print flow and power edits for peak and average assemblies	True
zoningStrategy	Channel Grouping Options for Safety;everyFA: every FA is its own channel, byRingZone: based on ringzones, byFuelType: based on fuel type, Manual: you must specify ‘zoneDefinitions’ setting	byRingZone