pebbed6 input manual - catatan studi tsdipura · word 1: sor flux (inner) acceleration parameter (1...

PEBBED6 Input Manual

Topan Setiadipura (BATAN) @INL Visit, 4 Sept 2015

General Input Specification

Card 00001 Title

HTR10_crit.inp : HTR10 Case IC UC D0 lsc uni 0.61

Input Information HTR10_crit.inp

Word 1 : Title of analysis or calculation (80 character sting)

HTR10 Case IC UC D0 lsc uni 0.61

Card 00002 Problem Definition HTR10_crit.inp : 00002 1 2 1 1 2 50 1 94


Word 1 : Prolem Type Selection (ptype)

=0 , geometry/composition edit only =1, initial loading eigenvalue =2, OTTO –initial and asymptotic =3, RECIRC – initial and asymptotic cont. refueling. =4, RESTART –perturbation of previous solution =5, BATCH – batch refueling

1

Word 2 : Number of Dimensions (ndim = 1,2, or 3) 2

Word 3 : Geometry selection (geo) =0, cartesian =1, cylindrical =2, spherical (1D only – may be buggy)

1

Word 4 : Modeled (1D) or Excluded (2D) Plane (sdim = 1,2,or 3) 2

Word 5 : Number of Cells in Mesh for 1D (NR , 120 max) 50

Word 6 : Number of Cells in Mesh for 2D (NQ, 120 max) 1

Word 7 : Number of Cells in Mesh for 3D (NZ, 120 max) 94

Card 00003 Neutronic/Albedo boundary condition (0 = flux is zero, 1 = current is zero)

HTR10_crit.inp : 00003 1 0 1 1 0 0


Word 1 : Inner boundary condition for X or R direction 1

Word 2 : Outer boundary condition for X or R direction 0

Word 3 : Inner boundary condition for Y or θ direction 1

Word 4 : Outer boundary condition for Y or R direction 1

Word 5 : Inner boundary condition for Z 0

Word 6 : Outer boundary condition for Z 0

Card 00004 Convergence Parameters

HTR10_crit.inp : 00004 5 2 1000 2000 8 8 8


Word 1 : Initial max. number of inner iterations per source iteration* and

also the upper limit on the number of thermal upscatter iterations*

5

Word 2 : Positive increment to initial max. number of flux iterations per source iteration.

2

Word 3 : Max. number of iterations for flux convergence 1000

Word 4 : Max. number of iterations for source convergence 2000

Word 5 : Max. number of iterations for burnup convergence 8

Word 6 : Max. number of iterations for entry plance burnup convergence 8

Word 7 : Max. number of iterations for discharge plane burnup convergence

8

*For the finite difference solver, the max. of inner (flux) iterations is initially set at this number then incremented upward by Word 2 on each outer (source) iteration, up to the value of Word 3. This prevents too much computational effort in converging the flux shape before the source is converged. For the nodal solver, this scheme controls the number of leakage iterations between the 1-D flux sweeps.

Card 00005 Convergence Criteria HTR10_crit.inp : 00005 5E-5 1.0E-7 1.0E-3 1.0E-4 5.0E-3 0.05 1.0E-4


Word 1 : Max. tolerance for flux convergence 5E-5

Word 2 : Max. tolerance for source convergence 1.0E-7

Word 3 : Max. tolerance for local burnup convergence 1.0E-3

Word 4 : Max. tolerance for entry plane burnup convergence 1.0E-4

Word 5 : Max. tolerance for discharge plane burnup convergence 5.0E-3

Word 6 : Max. tolerance for source term extrapolation 0.05

Word 7 : Max. flow zone flow fraction that is neglected in property averaging and the min. spectral zone volume that is accepted for cross section processing.

1.0E-4

Card 00006 Misc. Solution (method) Options

HTR10_crit.inp : 00006 2 0 0


Word 1 : = 0, No Source or SOR acceleration = 1, Source acceleration = 2, Source and SOR acceleration (finite difference)

2

Word 2 : Flux Solver = 0, Finite difference = 1, Coarse Mesh Finite Difference (CMFD) Nodal !!1D and some 2D problems only so far.

0

Word 3 : = 0, Do not use nuclide densities from previous case = 1, Use nuclide densities from previlus case =2, Read fluxes and nuclide densities from a restart file

0

Card 00007 Energy group number and Cross-section input options

HTR10_crit.inp : 8 4 3 3


Word 1 : Total number of energy groups ( 8 max) 8

Word 2 : Number of thermal groups 4

Word 3 : Number of fuel isotopes (1≤n≤3): If negative, isotopes listed on card 40000 will be used in place of ones provided in the nuclide/chain set (see card 00010)

3

Word 4 : Spectral zone-wise cross-section input option (inpxs) = 0, user defined in input deck = 1, no longer used = 2, 4-group microscopic cross-section from VSOP generated tables = 3, Cross-sections read from COMBINEv7-generated files specified on 190XX cards with COMBINE-7 called as a subroutine. Core plane cross sections will be coalesced form 1D ANISN models with buckling from axial and azimuthal leakage. = -3, Cross-sections read from COMBINEv7-generated files specified on 190XX cards with COMBINE-7 called as a subroutine. COMBINE inputs will be generated for each spectral zone with buckling computes from 3D leakage. = 4, 2-group Macroscopic Cross-section in OECD PBMR400 S-1 format = 5, 2-group macroscopic cross-section interpolated from tables in OECD PBMR400 S-3 format.

3

Card 00008 Fission Source Fraction (χ, Chi value)

HTR10_crit.inp : 00008 0.95064 0.04788 1.4805E-03 5.0290E-06 0.0 0.0 0.0 0.0

Input Information* HTR10_crit.inp

Word 1 : χ value for energy group 1 0.95064


Word 3 : χ value for energy group 3 1.4805E-03

Word 4 : χ value for energy group 4 5.0290E-06





*Number of inputs (words) in Card 00008 is defined by Word 1 in Card 00007 Last 4-group is thermal energy groups.

Card 00009 Energy group boundaries (eV)

HTR10_crit.inp : 00009 2.E7 1.83E5 7102. 2035. 2.38 1.5 0.42 0.12

Input Information* HTR10_crit.inp

Word 1 : Outer energy boundary for group 1 2.E7

Word 2 : energy boundary between group 1 and group 2 1.83E5

Word 3 : energy boundary between group 2 and group 3 7102.

Word 4 : energy boundary between group 3 and group 4 2035.

Word 5 : energy boundary between group 4 and group 5 2.38




*Number of inputs (words) in Card 00009 is defined by Word 1 in Card 00007 Last 4-group is thermal energy groups.

Card 00010 Number of Isotopes, Compositions, Spectral zones, and Nuclide Set selection

HTR10_crit.inp : 00010 90 85 660 4


Word 1 : Number of user-Supplied Nuclides (added to the number in the

selected set if Word 4 >0 )

90

Word 2 : Number of compositions 85

Word 3 : Number of Spectral zones (if < 0, alternative geometry input will be used)

660

Word 4 : Nuclide/Chain set number = 0, nuclide/chain data is provided by user In input = 1, for the basic set (C, O, Si, He, U`s and Pu`s) = 2, same as 1 but add Cm`s and Am`s = 3, the VSOP FP44 set plus H-1, He-4, N-14, and free gas O-16 (83 isotopes) = 4, set 3 plus Cs-137, Ag110m, 5 Pd, Th-231, Pa-231, Pa-232, and U-232 (93 isotopes) = 5, set 3 plus Cs-137, Ar-40, and 6 Hf isotopes, (91 isotopoes).

4

Card 00011 Acceleration Parameters (real)

HTR10_crit.inp : 00011 1.43 1.0 0.05


Word 1 : SOR flux (inner) acceleration parameter (1 ≤ ω ≤2.0) 1.43

Word 2 : Reference eigen value for reactivity calculations (default = 1.0) and the target eigenvalue for criticality searches (see card 00700 Word 2)

1.0

Word 3 : Source acceleration (outer) parameter (1 ≤ σf ≤2.0) 0.05

Card 00012 Number of moments used in nodal flux-source construction

HTR10_crit.inp : 00012 3


Word 1 : Number of moments used in (axial) flux & soruce construction 3

Card 00013

Card 00014 Resolved resonance options (real)

HTR10_crit.inp : 00014 2.0 0.01


Word 1 : Bondarenko or Nordheim resolved resonance treatment (inpxs = 3

only) = 0.0, evaluate all resolved resonances using Bondarenko interpolation (fast) = 1.0, evaluate all resolved resonances using Nordheim Integral Treatment (NIT) (slow) = 2.0, evaluate resolved resonances using NIT for all isotopes which the fractional contributions to the total zone absroption rate exceed the threshold on Word 2, otherwise use Bondarenko.

2.0

Word 2 : Fractional absroption threshold above which the NIT is used for resolved resonances in a given isotope (default, 0.001)

0.01

Card 00015 Variable output Options (least verbose most verbose)

HTR10_crit.inp : 00015 4 2 0 1 1 0


Word 1 : Output flag for solution -(+/- 0-6) , prints to file:(pbsoln.dat) 4

Word 2 : Output flag for flux –(-10-2) >1, prints coarse mesh fluxes to file: pbflux.dat =2, prints fine mesh flux to file: pbfmflux.dat =3, prints fine mesh flux to file: pbfmflux.dat but writes it in a format that can be read by MATLAB. =-1, READ flux map from pbfmflux.dat and skip flux calculation =-2, READ spectral zone fluxes from text file (VSOP) and skip flux calculation.

2

Word 3 : Output flag for Power Density distribution –(0-2) >1, prints coarse mesh power density to file: pbpower.dat. Also, coarse mesh temp. (avg. fuel, avg. pebble, peak fuel, avg. pebble surgace, and coolant) are printed to files. =2, prints fine mesh power density to file: pbfmpower.dat =3, prints fine mesh power density to file: pbfmpower.dat but writes it in a format that can be read by MATLAB. If fctemp=2, the fine mesh temp. will also be printed to files in MATLAB-readable format.

0

Word 4 : Output flag for Nuclide Densities (0-2) for nuclide specified on card 00040 = 1, prints coarse mesh avg. densities and transport mean free path to files: pbconc.dat, pbmfp.dat = 2, prints fine mesh avg. densities to file: pbconc.dat > 1, prints fine mesh capture and fission rates to file: pbabsrate.dat, pbfsnsrate.dat > 1, prints mean free path to file: pbmfp.dat (??)

1

Word 5 : Output flag for Burnup History –(0-1) prints to file: pbburn.dat = 1, prints node-wise burnup values to file: pbburn.dat = 2, also prints fissions concentrations and discharge burnup and nuclide distributions to files: pbfsncount.dat and pbburndist.dat

1

Word 6 : Output flag for zone wise microscopic cross-section (0-1, 1 prints to pbzonemicroxs.dat) 0

A negative sign for Word 1 directs the code to write a restart file provides the starting core configuration for subsequent runs that choose to use it (Word 3 Card 00006)

Card 00016 Burnup Distribution Statistical Parameters (if Word 5 on Card 00015 = 2)

HTR10_crit.inp : 00016 1.0 50


Word 1 : Edit frequency for pebble trajectories (0. ≤ bsample ≤ 1. ) 1.0

Word 2 : Number of bins for histogram generation ( 1. ≤ numbinsBd ≤ 200 ) 50

Card 00019 COMBINE spectral zone eigenvalue convergence criterion (|inpxs| == 3)

HTR10_crit.inp : 00019 -1.0 0.0 / 00019 0.002 0.0


Word 1 : Value of criterion below which spectral calculation is considered

converge. Default = tolBi. A value of -1.0 suspends the spectral iterations.

-1.0 / 0.002

Word 2 : Option to invoke nonlocal heating calculation (PHOTONCALC) = 0, no nonlocal heating (fission energy deposition is local) = 1, local fission heating plus gamma heating = 2, local fission heating plus gamma and neutron heating (using heating cross-section) = 3, local fission heating plus gamma and neutron heating (using KERMA cross-section)

0.0

Q: What happen if two same cards are active? Is the last one chosen ?

Card 00040 Nuclide Edit HTR10_crit.inp : 00040 16 15 16 17 18 19 29 43 41 42 (inactive / commented)


Word 1 : Number of nuclide of interest

Word 2 20 : Nuclide ID numbers for the nuclides for which burnup data are to be edited

Card 00050 Buckling option for COMBINE spectrum calculations

HTR10_crit.inp : 00050 1 1.0E-5 -1.5E-5


Word 1 : Buckling option for COMBINE spectrum

= 0, use the values on Words 2 and 3 = 1, compute group-wise buckling from zone leakages = 2, use material buckling computed from cross-sections (rarely used)

1

Word 2 : Input fast buckling (cm-2) (if Word 1 == 0) 1.0E-5

Word 3 : Input thermal buckling (cm-2) (if Word 1 == 0) -1.5E-5

Card 00051 Reduced feedback option (COMBINE updating only)

HTR10_crit.inp : 00051 omitted / inactive


Word 1 : Flag to turn off temp. or burnup feedback in cross section

generation = 0, temp. and burnup feedback included (default) = 1, no temp. feedback = 2, no burnup feedback = 3, no temp. and burnup feedback

If Card 00051 is not written, is the default active or is it same with use `0` value for Card 00051?

Card 00053 Diffusion Coefficient Option



Word 1 : = 0, diffusion coefficient computed from PEBBED-computed zone avg. number densities and microscopic transport cross-sections for groups ≥ Word 2 (Default) = ±1, diffusion coefficient computed from PEBBED-computed zone avg. number densities and microscopic transport cross-sections for groups ≥ Word 2 = ±2, diffusion coefficient computed from Fick`s Law (radial current and radial flux gradient from B-1, B-3 solution) for groups ≥ Word 2 = ±3, diffusion coefficients computed from (multi-zone COMBINE 1-D runs only – diffusion coefficients above and below core are computed from microscopic transport cross-sections).

0

Q: What is the different between 0 and ±1 values for Card 00053 ? both explanations are exactly the same as in the PEBBED6 Manual.

Card 00054 Editing of additional cross-section by COMBINE



Word 1 : Flag to edit additional cross section by COMBINE = 0, edit only the minimum set of cross-sections for a diffusion/depletion calculation = 1, edit additional cross-sections such as (n,2n) needed for some chains.

0

This value is automatically set to 1 if Word 2 on Card 00019 > 1. )

Card 00060 Core power and total core Pebble Flow Rate

HTR10_crit.inp : 00060 0.0001 10450.0


Word 1 : Power generated in modeled region [MW] 0.0001

Word 2 : Total core pebble flow rate (Pebbles/day) 10450.0

Card 00061 Run-time used for Xe buildup

HTR10_crit.inp : 00061 0.0


Word 1 : Time to deplete a static core to build up Xenon (days) (Default = 5.0)

0.0

Card 00062 Batch load refueling parameters (ptyp == 5)

HTR10_crit.inp : inactive


Word 1 : Time (days) of the burnup cycle

Word 2 : Number of equivalent volume batches comprising a full core

Word 3 : Flag* for time in cycle at which restart file is edited and cross seections are update

Word 4 : Flag* for time in cycle at which DLOFC transient is executed (if loga=2: Word 2 on Card 50000)

* 0. for Beginning of Cycle (BOC), 1. for Midle of Cycle (MOC), 2. for End of Cycle (EOC)

Card 00070 Axial Pebble Velocity Profile

HTR10_crit.inp : 00070 0.0 0.0


Word 1 : Coefficient of quadratic term in entry plane velocity profile 0.0

Word 2 : Coefficient of linear term in entry plane velocity profile (Constant term default = 1)

0.0

By the above input, is it a homogeneous velocity along the entry plane ?

Geometry Specification

Coarse mesh boundaries are specified by the mesh widths given on the following 0010X, 0020X, and 0030X cards.

Compositions are laind out as a map on cards 02101-02399. Spectral zone are lain out as a map on cards 03101-03399.

Number of pebble flow channels and flow channel boundaries are computed automatically form the coarse mesh specification.

Card 0010X Material zone mesh interval definitions for the X or R dimension.

HTR10_crit.inp : contain following 5 cards for radial (R) direction 00101 3 -4 13.0 -4 12.0 -4 14.0 00102 3 -4 11.0 -4 10.0 -4 10.5 00103 2 -4 13.0 -2 6.5 00104 5 2 5.6 4 13.0 4 32.0 2 8.0 4 18.9

00105 2 2 11.3 2 11.2

Input Information HTR10_crit.inp **

Word 1 : The number (P) of zone pairs* (number of intervals and coarse

mesh interval width) on card 0010X

3, 3, 2, 5, 2 (for the above

card succesively)

Word 2 : Number of fine mesh interval in first coarse mesh interval -4

Word 3 : width of first mesh interval 13.0





If P = p, then for that card, after Word 1, will need another 2*p cards. **values given for Card 00101 only as example, except for Word 1.

Card 0020X Material zone mesh interval definitions for the Y or θ dimension.

HTR10_crit.inp : 00201 1 1 360.

Input Information HTR10_crit.inp **



1

Word 2 : Number of fine mesh interval in first coarse mesh interval 1

Word 3 : width of first mesh interval. 360.

The R-Z model is actually a R-θ-Z model, however the azimuthal (θ) direction is a single mesh.

Card 0030X Material zone mesh interval definitions for the Z dimension.

HTR10_crit.inp : contain following 9 cards for axial (Z) direction 00301 5 4 40.0 5 55.0 2 10.0 2 9.7 2 15.3 (Top reflector) 00302 1 4 41.698 (Void) 00303 6 2 9.006 2 9.006 2 9.006 2 9.006 2 9.006 2 9.006 (core for next 4 cards) 00304 6 1 3.024 -1 5.982 -2 9.006 -2 9.006 -2 9.006 -2 9.006 00305 6 -2 9.006 -2 9.006 -2 9.006 -2 9.006 -2 9.006 -2 9.006 00306 3 -2 9.006 -2 9.006 -2 9.006 00307 5 2 7.3892 2 7.3892 2 7.3892 2 7.3892 2 7.3892 (Conus, chute, bottom reflector, for next 3 cards) 00308 6 1 4.412 1 4.412 1 4.412 3 28.0 3 20.0 1 15.0

00309 6 1 30.0 1 1.0 1 1.0 2 13.0 3 30.0 7 70.0

Input Information HTR10_crit.inp (only for 00306 as example)



3







Pebble Specification

•Pebbles can be homogeneous (composed only of graphite), singly-heterogeneous (composed of an inner absorber or fuel zone and an outer shell), or doubly-heterogeneous (composed of a shell surrounding a fuel region that contains fuel particles in a carbon matrix). •Each pebble type is linked to a composition specified on the 3xx00 cards. •The core can consist of a single type or a mixture of pebble types. •The core is split into flow zones specified denoted by negative values on the 0010x cards. •The core can also be split into an inner and outer core into which the pebbles can be loaded at specified rates.

Card 50001 Pebble radius (cm), Fuel radius (cm), and Void Fraction

HTR10_crit.inp : 50001 3.0 2.5 0.61


Word 1 : Pebble outer radius 3.0

Word 2 : Radius of fuel in pebble 2.5

Word 3 : void fraction within core 0.61

This card actually part of Thermal Fluid Specification, but also included here

Card 00700 Number of pebble types

HTR10_crit.inp : 00700 -2 1 5


Word 1 : Number of pebble types

If this value is negative then the different pebble types are mixed according to the flow partition coefficients to yield the appropriate compositions for the pebble bed when there is more than one pebble type.

-2

Word 2 : Pebble Type for which the Discharge Burnup is used to adjust flow rate (principle pebble). If this value is negative the for equilibrium calculations the flow rate will be adjusted to achieve the target eigenvalue input on Card 11. Otherwise, the flow rate will be adjusted to achieve the desired discharge burnup.

1

Word 3 : Number of layers comprising the coated particles (including the matrix material)

5

Card 00701 Ex-core decay time HTR10_crit.inp : 00701 0.0 0.0


Word 1 : Ex-core decay time (h) for pebble type 1 0.0

Word 2 : Ex-core decay time (h) for pebble type 2 0.0

Is it time neede to recirculate pebbles from its discharge to finally put again in the core ?

Card 00702 Pebble Fuel Labels HTR10_crit.inp : 00702 Fuel Dummy


Word 1 : (Max.) 6-character label for pebble type 1 Fuel

Word 2 : (Max.) 6-character label for pebble type 2 Dummy

Card 00703 Pebble Target Burnup HTR10_crit.inp : 00703 80.0 0.0


Word 1 : Target discharge burnup (MWD/Kg) for pebble type 1 80.0

Word 2 : Target discharge burnup (MWD/Kg) for pebble type 2 0.0

Card 00704 Pebble Composition HTR10_crit.inp : 00704 1 85


Word 1 : Composition ID for pebble type 1 1

Word 2 : Composition ID for pebble type 2 85

Card 00705 Recycle Mode for Pebble Type p

HTR10_crit.inp : 00705 0 0


Word 1 : Recycle mode ID for pebble type 1 (recmod)

= 0, random recycle (single type) = 1, pebble channeling (single type) =± 2, two-zone recirculation scheme with pass-independent recirculation =± 3, two-zone recirculation scheme with pass-dependent recirculation = 4, zone and transfer partition coefficients to be supplied by user in pbrec.dat file

0

Word 2 : Composition ID for pebble type 2 (recmode) (same options as Word 1)

0

Card 00706 Two-zone core flow parameters

HTR10_crit.inp : INACTIVE


Word 1 : Fraction of Total Pebble flow in outer zone of a Two Zone Core

Word 2 : Width (cm) of mixing region in 2-zone core

Word 3 : Distribution Model for pebbles in mixing zone: (mixopt) = 0, No redistribution, pebble composition is uniform across mixing zone = 1, Pebble composition varies linearly across mixing zone = 2, Pebbl composition varies sinusoidally across mixing zone

Card 00707 Transfer Partition Coefficient File



Word 1 : Name of file containing transfer partition coefficients ( up to 18

char.acter in length)

Card 00708 Composition fraction of pebble type p in Outer Annulus* (|recmod(p)|=0, 2, or 3 only)

HTR10_crit.inp : 00708 0.57 0.43


Word 1 : Fraction of flow in outer zone composed of pebble type 1 0.57

Word 2 : Fraction of flow in outer zone composed of pebble type 2 0.43

*Outer annulus is entire core in single zone cases.

Card 00709 Composition fraction of pebble type p in Inner Zone (|recmod(p)|=2, or 3 only)



Word 1 : Fraction of flow in inner zone composed of pebble type 1

Word 2 : Fraction of flow in inner zone composed of pebble type 2

Card 00710 Target Burnup for Nuclide Edit

HTR10_crit.inp : 00710 80.0 0.0


Word 1 : Burnup at which nuclide in pebble type 1 are to be edited 80.0

Word 2 : Burnup at which nuclide in pebble type 2 are to be edited 0.0

Q: what is the different with Card 00703? Should we use both?

Card 00711 Fixed number of passe per pebble

HTR10_crit.inp : 00711 20 1


Word 1 : Number of passes for pebble type 1 20

Word 2 : Number of passes for pebble type 2 1

Card 00712 Number of particle per pebble

HTR10_crit.inp : 00712 8334. 0.0


Word 1 : Number of particles in pebble type 1 8334.

Word 2 : Number of particles in pebble type 2 0.0

Card 00713 Radius of kernels in particles of pebble type p

HTR10_crit.inp : 00713 0.025 0.0


Word 1 : Kernel radius in pebble type 1 [cm] 0.025

Word 2 : Kernel radius in pebble type 2 [cm] 0.0

Card 00714 Radius of Fuel Zone in pebble type p

HTR10_crit.inp : 00714 2.5 0.0


Word 1 : Fuel zone radius in pebble type 1 [cm] 2.5

Word 2 : Fuel zone radius in pebble type 2 [cm] 0.0

Card 00715 Radius of Pebble type p

HTR10_crit.inp : 00715 3.0 3.0


Word 1 : Radius in pebble type 1 [cm] 3.0

Word 2 : Radius in pebble type 2 [cm] 3.0

Card 00716 Particle Dancoff (INTRA) factor in pebbles of type p

HTR10_crit.inp : 00716 0.226 0.0 or 00716 0.2329 0.0


Word 1 : Partilce (INTRA) dancoff factor in pebble type 1 0.226 / 0.2329 **

Word 2 : Partilce (INTRA) dancoff factor in pebble type 2 0.0

**second value is computed by PEBDAN code.

Card 00717 Particle Dancoff (INTER) factor in pebbles of type p

HTR10_crit.inp : 00717 0.0204 0.0204 / 0.032 0.032 / 0.0519 0.0 **


Word 1 : Partilce (INTER) dancoff factor in pebble type 1 0.0204 / 0.0302 / 0.0519

Word 2 : Partilce (INTER) dancoff factor in pebble type 2 0.0204 / 0.0302 / 0.0

**The values are given by following assumption: - Fuel : Graphite mixture according to Bende - Fuel : Graphite mixture according to PEBDAN - Separate pebbles according to PEBDAN.

Card 00718 Peaking Factors HTR10_crit.inp : 00718 1.0 1.0


Word 1 : Ratio of peak to mean power density in pebble type 1 1.0

Word 2 : Ratio of peak to mean power density in pebble type 2 1.0

Q: Is it include the shell zone of pebble or only the fuel zone are (that the power density is homogeneous) ?

Card 00720 Particle Composition Data

HTR10_crit.inp : 00720 5 1 3 4


Word 1 : Number of isotopes composing the particle layers (<= 8) 5

Word 2 : Number of adsorbed moderator isotopes in the kernel (<= 3) 1

Word 3 : Number of adsorbed absorber isotopes in the kernel (<= 3) 3

Word 4 : Number of isotopes composing the coolant (<= 8) 4

Card 00721 Nuclide ID numbers of isotopes in particle layers

HTR10_crit.inp : 00721 78 76 79 73 74


Word 1 : ID of nuclide 1 in particle layers 78





Number of isotopes is defined by Word 1 of Card 00720.

Card 00722 Nuclide ID numbers of adsorbed moderators in the kernel.



Word 1 : ID of adsorbed moderator 1 in kernel 79

Number of adsorbed moderator is defined by Word 2 of Card 00720.

Card 00723 Nuclide ID numbers of adsorbed absorbers in the kernels

HTR10_crit.inp : 00723 6 9 16


Word 1 : ID number of adsorbed absorber 1 6



Number of adsorbed moderator is defined by Word 3 of Card 00720.

Card 00724 Nuclide ID numbers of coolant isotopes

HTR10_crit.inp : 00724 81 80 90 89


Word 1 : ID number of coolant isotopes 1 81 (He)

Word 2 : ID number of coolant isotopes 2 80 (H)

Word 3 : ID number of coolant isotopes 3 90 (O)

Word 4 : ID number of coolant isotopes 4 89 (N)


Card 00725 Nuclide density of coolant isotopes

HTR10_crit.inp : 00725 6.522E-04 1.718E-07 1.100E-05 3.781E-05


Word 1 : Density of coolant isotopes 1 [atom/b.cm] 6.522E-04





Card 00727 – 00730 Related with Burnable Poison Particle (BPP) are INACTIVE in current HTR10_crit.inp

Card 00731 Thicknesses of TRISO particle layers in Pebble Bed Type 1

HTR10_crit.inp : 00731 0.009 0.004 0.0035 0.004 0.0778


Word 1 : Thickness of layer 1 [cm] 0.009





This is part of Card 0073p for each Pebble Bed Type `p`. Number of pebble bed type is given in Word 1 Card 00700. Number of layers is given by Word 3 Card 00700. The TRISO layers are 1. buffer, 2. inner pyrolitic carbon (IPyC), 3. Silicon Carbide (SiC), 4. outer pyrolitic carnon (OPyC), and 5. graphite matrix. Q: How is to calculate the thickness of the graphite matrix layer ?

Card 00732 Thicknesses of TRISO particle layers in Pebble Bed Type 2

HTR10_crit.inp : 00732 0.009 0.004 0.0035 0.004 0.0778 !ignored







This is part of Card 0073p for each Pebble Bed Type `p`. Number of pebble bed type is given in Word 1 Card 00700. Number of layers is given by Word 3 Card 00700. The TRISO layers are 1. buffer, 2. inner pyrolitic carbon (IPyC), 3. Silicon Carbide (SiC), 4. outer pyrolitic carnon (OPyC), and 5. graphite matrix. In this HTR10_crit.inp pebble bed type 2 is dummy graphite, so this input will be ignored.

Card 00741 Number densities of non-depleting isotopes in kernels in pebble type 1

HTR10_crit.inp : 00741 0.00E+00 0.00E+00 4.6646E-02 4.393E-07 1.608E-06


Word 1 : Number density of isotope 1 [atoms/b.cm] 0.00E+00


Word 3 : Number density of isotope 3 [atoms/b.cm] 4.6646E-02 / 4.6671E-02



This is part of Card 0074p for each Pebble Bed Type `p`. Number of pebble bed type is given in Word 1 Card 00700. The number of isotopes is given in Word 1 Card 00720, and ID numbers of each are given in Card 00721 as following 1. C, ID number 78 2. Si, ID number 76 3. O, ID number 79 4. B-10, ID number73 5. B-11, ID number 74

Card 00751 Number densities of nondepleting isotopes in layer 1 (buffer) in pebble type 1

HTR10_crit.inp : 00751 5.515E-02 0.00E+00 0.00E+00 1.714E-08 6.271E-08


Word 1 : Number density of isotope 1 [atoms/b.cm] 5.515E-02





This is part of Card 0071p for each Pebble Bed Type `p`. Number of pebble bed type is given in Word 1 Card 00700. This is part of Card 0075p for each Pebble Bed Type `p`. Number of pebble bed type is given in Word 1 Card 00700. The number of isotopes is given in Word 1 Card 00720, and ID numbers of each are given in Card 00721 as following 1. C, ID number 78 2. Si, ID number 76 3. O, ID number 79 4. B-10, ID number73 5. B-11, ID number 74

Card 00761 Number densities of nondepleting isotopes in layer 2 (IPyC) in pebble type 1

HTR10_crit.inp : 00761 9.526E-02 0.00E+00 0.00E-00 2.960E-08 1.083E-07








Card 00771 Number densities of nondepleting isotopes in layer 3 (SiC) in pebble type 1

HTR10_crit.inp : 00771 4.775E-02 4.775E-02 0.00E-00 1.484E-08 5.430E-08








Card 00781 Number densities of nondepleting isotopes in layer 4 (OPyC) in pebble type 1









Card 00791 Number densities of nondepleting isotopes in layer 5 (Graphite Matrix) in pebble type 1









Card 00742 Number densities of nondepleting isotopes in layer kernels in pebble type 2









Card 00752 Number densities of nondepleting isotopes in layer 1 (buffer) in pebble type 2









Card 00762 Number densities of nondepleting isotopes in layer 2 (IPyC) in pebble type 2









Card 00772 Number densities of nondepleting isotopes in layer 3 (SiC) in pebble type 2









Card 00782 Number densities of nondepleting isotopes in layer 4 (OPyC) in pebble type 2









Card 00792 Number densities of nondepleting isotopes in layer 5 (Matrix Graphite) in pebble type 2









Card 00811 Number densities of nondepleting isotopes in SHELL region in pebble type 1









Card 00812 Number densities of nondepleting isotopes in SHELL region in pebble type 2









Composition and Spectral Zone Assignment

- Each region (spectral zone) of the model is assigned a composition (some of whichare pebbles) form the list on the 3XX00 cards. - Cross sections are computed for each of these zones using local temperature and composition data. - Some of the data for each zone can be set in advance, modified or over-written.

Card 01500 Ambient Zone Temperature

HTR10_crit.inp : 01500 288.15


Word 1 : Temperature of default ambient zone (Zone 1) [K] 288.15

Card 015XX Initial guess for Zone Temperatures



Word 1 : Temperature [K] of zone (XX-1)*10 + 1


…… (continue with same pattern)


Card 016XX Inter-pebble dancoff multiplication factor for individual zones



Word 1 : Factor by which core-avg. inter-pebble dancoff is multiplied to

adjust for location in zone (XX-1)*10 + 1

Word 2 : Factor by which core-avg. inter-pebble dancoff is multiplied to

adjust for location in zone (XX-1)*10 + 2


Word 10 : Factor by which core-avg. inter-pebble dancoff is multiplied to adjust for location in zone (XX-1)*10 + 10

Card 02100 Name of file containing the 3D composition map (ndim = 3 only)



Word 1 : Name of text file containing the 3D composition map (<= 18 char.)

For inpxs not equal to 3, this file also contains the spectral zone map.

Card 021XX 2D* (x-y, r-z) Composition Assignment

HTR10_crit.inp : (see figure besides)


Word 1 : Composition # in radial coarse mesh

interval #1, axial coarse mesh interval XX

1 (from 00214 as example)





Word 10 : Composition # in radial coarse mesh interval #10, axial coarse mesh interval XX


The HTR10_crit.inp model contain 44 radial coarse meshes, 15 radial coarse meshes. - Axial coarse mesh represented by XX is started from 01 to 44. - Radial dimension is limited to 10 radial coarse mesh. It is continue in Card 022XX.

Card 022XX 2D* (x-y, r-z) Composition Assignment

HTR10_crit.inp : (see figure besides)









Word 10 : Composition # in radial coarse mesh interval #10, axial coarse mesh interval XX


The HTR10_crit.inp model contain 44 radial coarse meshes, 15 radial coarse meshes. - Axial coarse mesh represented by XX is started from 01 to 44. - Radial dimension is limited to 10 radial coarse mesh. Card 022XX start from 11th radial coarse of the model, containing 5 radial coarse mesh.

A complete Composition Assignment is represented by joining Card 021XX and 022XX

θ

Note :

• Composition 18,80-73,65,56,47 have a high Boron concentration.

• Where is the control rod composition? And riser composition?

Card 031XX (x-y, r-z) Spectral zone assignment (for inpxs not equal to 3

only, not usually needed)

Q: Then how the spectral zone is defined in HTR10 case ?

Card 20000 Global cross-section input file (mcxfile)

HTR10_crit.inp : HTR10_8gset4


Word 1 : Name of default COMBINE cross-section file to be read (<= 18 char.) HTR10_8gset4

Nuclide Specification

- Some nuclide sets and their associated burnup chains are hard-wired in PEBBED and offered as user options (Word 4 on Card 00010). - One can over-write specific nuclide data or add to the set using the following cards. -These cards must be included if Word 4 on Card 00010 is set to 0

Nuclide Specification input in HTR10_crit.inp

What Card/input are these lines ?

-Why Cards 23010 have 7 Words, it is 6 Words in the PEBBED6 Manual ? - Is it defining a 6-group principal cross-section ? - What input is the Cards 23011 – 23016 ??

Card 2XX00 Nuclide Label (XX=Nuclide ID Number)

HTR10_crit.inp : 23000 VCLFP 0


Word 1 : Nuclide Name of Symbol (6character) VCLFP 0

Card 2XX10 Nuclide Label (XX=Nuclide ID Number)

HTR10_crit.inp : 23010 99. 0. 0. 0. 0. 0. 0. / 99. 0. 1.1203 0.9476 1.156 1.104 0.


Word 1 : Molecular Weight of Nuclide 99.

Word 2 : Decay Constant (lambda) of Nuclide 0.

Word 3 : Fission Yield of Nuclide from Fuel Isotope 1 0. / 1.1203



Word 6 : Energy per Fission of Nuclide (MeV) 0. / 1.104

Word 7 : ??? (in HTR10_crit.inp) 0.

Number of Fuel Isotope is given by Word 3 Card 00007. In HTR10_crit.inp there are 3 Fuel Isotope.

Card 2XX0g Principle Cross-Section (g = group number)

HTR10_crit.inp : (for 6-groups)

23001 1.566E-02 1.574E-02 0. 0. 23002 0.7994 0.7983 0. 0. 23003 0.7994 0.7983 0. 0. 23004 0.1070 0.1069 0. 0. 0. 23005 0.1070 0.1069 0. 0. 0. 23006 6.707 0.5005 0. 0. 0.

Input Information HTR10_crit.inp *

Word 1 : Transport cross-section 1.566E-02

Word 2 : Absorption cross-section 1.574E-02

Word 3 : Nu*Fission Cross-section 0.

Word 4 : Fission Cross-section 0.

*only for 23001 (n=1) as example.

Composition Specification

- Compositions are mixture of nuclides representing a material in the model. -Compositions can be homogenous (no structure) or heterogenous. -For heterogenous compositions, information on the geometry must also be supplied along with the nuclide information.

Card 30001 Enrichment (w/o) of composition of prinsipal pebble type (optional)



Word 1 : Weight perecentage of U-235 that will be used to re-compute the

enrichment of uranium in the composition used on the primary pebble type (see Card 700, Word 2 and Card 704)

For each of Composition (ID Number = XX) • 3XX00 : Composition Label • 3XX01 : Number of Nuclides in Composition • 3XX02 : Composition Geometry Heterogeneity • 3XX11 : List of Nuclide IDs in Composition • 3XX21 : List of Homogeneous Nuclide Densities [atoms/b.cm] in Composition • 3XX30 : Thicknesses of region in composition • 3XX31 : Number of mesh intervals into which each composition region is to be subdivided in

the ANISN unit cell model • 3XX32 : Thicknesses of the additional driver zone region in Composition • 3XX40 : List of Nondepletable Nuclide IDs in Composition Regions (must be a subset of those

specified on 3XX11) • 3XX4p : Densities of nondepletable Nuclide IDs in Composition region p • 3XX4p (??): List of Homogeneous Nuclide Densities [atoms/b.cm] in composition region p. • 3XX80 : Dimension of Void above Core for computing Diffusion Coefficients for Void

Composition XX. • 3XX8g : Replacement Directional Diffusion Coefficients for Composition XX, group g. • 3XX9g : Replacement Directional Diffusion Coefficients for Composition XX, group g+10

Card 3XX00 Composition Label (XX = Composition ID Number)

HTR10_crit.inp* : 30100 Fuel (XX = 01)

302100 Top_refl4 (XX = 02)


Word 1 : Composition Name (fuel, reflector, core, etc.) Fuel / Top_refl4

*The given values are for ID Numbers = 01 (Fuel) and 02 (One of Top Reflector) compositions, as example. There are totally 85 compositions in HTR10_crit.inp model.

Card 3XX01 Number of Nuclides in Composition

HTR10_crit.inp* : 30101 0 (XX = 01) 302101 3 (XX = 02)


Word 1 : Number of Nuclides in composition XX

-A negative value indicates that the mixture is depletable - A value of 0 indicates that all (nnuc) nuclides in the model are included in the composition and the mixture is depletable (ptype == 5, batch or refuling, only so far).

0 / 3

*The given values are for ID Numbers = 01 (Fuel) and 02 (One of Top Reflector) compositions, as example. There are totally 85 compositions in HTR10_crit.inp model.

Card 3XX02 Composition Geometry Heterogeneity

HTR10_crit.inp* : 30102 3 0 0 2 (XX = 01) 30202 0 1 0 0 (XX = 02)


Word 1 : Geometry ID of composition XX

= 0, homogeneous mixture = 1, slab geometry with layers (e.g. heterogeneous axial plates) = 2, cyclindrical geometry with anuli (e.g. control rods) = 3, spherical geometry with shells (e.g. pebbles)

3 / 0

Word 2 : Number of regions in composition XX if [0 <Word 1 <3] 0 / 1

Word 3 : Number of nuclides in regions in composition XX if [0 <Word 1 <3], spherical compositions are specified on 007xx cards.

0 / 0

Word 4 : Levels of Heterogeneity in Composition XX = 0, no heterogeneity (default) = 1, structure on only 1 spatial sclae (e.g. Control Rod) = 2, Microsphere internal structure

2 / 0

For double hetergogeneity, Word 1 specifies the geometry of the first (macro) level. At the 2nd (micro) level, the geometry is assumed spherical (e.g. KLAK spheres in a SAS channel). * As example, the given values are for ID Numbers = 01 (Fuel) and 02 (One of Top Reflector) compositions, respectively. There are totally 85 compositions in HTR10_crit.inp model.

Card 3XX11 List of Nuclide IDs in Composition

HTR10_crit.inp* : 30111 78 6 9 79 73 74 80 (XX = 01) 30112 89 90 81 30211 73 74 78 (XX = 02)


Word 1 : First Nuclide ID Number in composition XX 78 / 73

Word 2 : Second Nuclide ID Number in composition XX 6 / 74

…continue with the same pattern for next nuclide.

Word n : Last Nuclide ID Number in composition XX (n in the number of nuclide given in Card 3XX01.)

80 / 78

If Word 1 Card 3XX01 is set to be zero, the densities of all the nuclides in the composition are set to an initial value of zero except for the nuclides specified in this cards. The initial values of these nuclides are given on card 3XX21. •As example, the given values are for ID Numbers = 01 (Fuel) and 02 (One of Top Reflector) compositions, respectively. There are totally 85 compositions in HTR10_crit.inp model. •The max. nuclide for one 3XX11 card is 8 nuclides, Card 30112 can be added for more nuclides as shown in Fuel Composition above.

Card 3XX21 List of Homogeneous Nuclide Densities [atoms/b.cm] in Composition

HTR10_crit.inp* : = C U235 U238 O16u Si28 [XX = 01] 30121 5.245E-02 1.175E-05 5.662E-05 1.367E-04 1.493E-04 = B-10 B-11 H-1 N-14 O-16f He

30122 1.6430E-08 6.614E-08 6.70059E-07 1.47464E-05 3.3503E-7 2.0E-04

= B10 B11 C [XX = 02] 30211 7.088954E-04 2.593994E-03 0.729410E-01


Word 1 : Smeared densitiy of FIRST Nuclide in Card 3XX11 5.245E-02 / 7.088954E-04

…continue with the same pattern for next nuclide.

Word n : Smeared densitiy of LAST Nuclide in Card 3XX11 1.493E-04 / 0.729410E-01

•As example, the given values are for ID Numbers = 01 (Fuel) and 02 (One of Top Reflector) compositions, respectively. There are totally 85 compositions in HTR10_crit.inp model. •The max. nuclide for one 3XX21 card is 8 nuclides, Card 30122 can be added for more nuclides as shown in Fuel Composition above.

Card 3XX80 Dimensions of Void above the Core for Computing Diffusion Coefficients for Void Composition XX

HTR10_crit.inp* : (include whole composition input for VOID, XX = 06) 30600 VOID 30601 6 30602 0 1 0 0 = B-10 B-11 C H O16f N 30611 73 74 78 80 90 89 = density [1/(b.cm)] 30621 3.260294E-13 1.193009E-12 8.9747e-06 1.718-07 1.1-05 3.781-05 30680 98.758 90.0 ! 123.06cm Card 3XX80 =30680 93.818 90.0 ! 128.0cm =30680 88.818 90.0 ! 133.00cm


Word 1 : Radius of void cavity [cm] 90.0

Word n : Height of void cavity [cm] 98.758

*The current input HTR10_crit.inp is mistakenly put Word 1 and Word 2.

Card 3XX8g Replacement Directional Diffusion Coefficients for Composition XX, group g

HTR10_crit.inp :Not Active/Needed in Fuel (XX = 01), below are only for XX = 02 for 8-group. 30281 1.805 1.805 1.805 30282 1.023 1.023 1.023 30283 0.975 0.975 0.975 30284 0.863 0.863 0.863 30285 0.511 0.511 0.511 30286 0.403 0.403 0.403 30287 0.230 0.230 0.230 30288 0.133 0.133 0.133


Word 1 : Radial diffusion coefficient 0.511 (g = 5, as example)

Word 2 : Azimuthal diffusion coefficient 0.511 (g = 5, as example)

Word 3 : Axial diffusion coefficient 0.511 (g = 5, as example)

•As example, the given values are for ID Numbers 02 (One of Top Reflector) compositions, respectively. There are totally 85 compositions in HTR10_crit.inp model, however not all compositions need Card 3XX8g.

Compositions with Card 3XX8g

θ

From all 85 compositions of the HTR10 model, these compositions ID need 3XX8g : -2, 3, 4, 5, 7, 8, 9, 10, 12,14,15, 17, 18, 84 : Reflectors - 85 : dummy ball.

- 11,13,19 no ? Why ? - all the side reflectors, no ?

Pebble and Coolant T/H Data

- PEBBED has a simple thermal-hydraulic solver built in as an option for both steady state core temperature profile and an analysis of core temperature during a depressuried loss of fluid transient (DLOF). - For better results, however, PEBBED can execute a two-dimensional THERMIX-KONVEK solution for both of these operating model. - A separate THERMIX-KONVEK input deck must be constructed for this purpose.

Card 50000 General T/H Options HTR10_crit.inp* : 50000 0 0 0 0 0


Word 1 : Flag to invoke fuel and coolant temperature distribution calculations

= 0, No T/H calculations, = 1, PEBBED 1D correlations for fuel, coolant temp = 2, THERMIX 2D calculation (requires a THERMIX-KONVEK input) = -2, THERMIX 2D calculation only (requires a THERMIX=KONVEK input and cell-wise powere densities on pbfmpower.dat)

0

Word 2 : Flag to invoke LOFA fuel temperature calculation = 0, No LOFA = 1, LOFA

0

Word 3 :Graphite conductivity (CONK) = 0, K-graphite is computed from a correlation = 1, K-graphite is Ks in reflector = 2, K-graphite is Ks in pebble and reflector.

0

Word 4 : Heat transfer correlation Flag = 0, KTA 3102.2 correlation (No) = 1, Gysler correlation = 2, RMM`s correlation > 2, KTA3102.2

0

Word 5 : Flag to invoke burnup dependent decay heat generation = 2, space-independent PBMR400 benchmark decay heat curve = 3, DIN 25485 standard

0

Card 50001 Pebble radius (cm), Fuel radius (cm), and Void Fraction

HTR10_crit.inp : 50001 3.0 2.5 0.61


Word 1 : Pebble outer radius 3.0

Word 2 : Radius of fuel in pebble 2.5

Word 3 : void fraction within core 0.61

This card written in Pebble Specification

Card 50002 Coolant Inlet Temp., Flow Rate, Spec. Heat, Pressure

HTR10_crit.inp* : 50002 250. 85.0 5190 6.0


Word 1 : Temp. of Coolant at Inlet [deg. C] 250.0

Word 2 : Mass Flow Rate of Coolant [Kg/s] 85.0

Word 3 : Specific Heat of Coolant [ J/Kg-K] 5190

Word 4 : Coolant Pressure at Core Inlet [Mpa] 6.0

Card 50003 Fuel and Shell Conductivity (W/m-K), Shell Density (g/cc)

HTR10_crit.inp* : 50003 20.0 20.0 1.75


Word 1 : Conductivity of Fuel Region (Kf) 20.0

Word 2 : Conductivity of Pebble Shell Region (graphite) (Ks) 20.0

Word 3 : Density of Shell region graphite 1.75

Card 50010 Temperature convergence criteria

HTR10_crit.inp* : 50010 1.E-4 1.E-3


Word 1 : Convergence criterion for fuel temp. iterations 1.E-4

Word 2 : Convergence criterion for coolant temp. iterations 1.E-3

Card 50500 THERMIX input file name HTR10_crit.inp* : 50500 HTR_Module_tmx.inp


Word 1 : name of THERMIX steady state input file (18 char. Or less) HTR_Module_tmx.inp

Card 52005 Graphite Reflector Fluence and Outer Boundary Temperature

HTR10_crit.inp* : 52005 0. 20. 3600.


Word 1 : Avg. Fluence or Effective Fuel Power Years of Irradiation in graphtie

reflector <= 100, Word 1 is the EFPY of operation of the reflector > 100, Word 1 is the fast fluence to which all of the reflector has been exposed

0.0

Word 2 : Outer boundary temperature (deg.C) of Outer LOFA region (constant) 20.0

Word 3 : Time interval between THERMIX DLOFC thermal map edits (sec) 3600.

Card 53001 Time Blocks HTR10_crit.inp* : 53001 3 10 1.0 59 10.0 300 1200


Word 1 : Number of intervals in tIme Block x 3

Word 2 : Duration (s) of intervals in Time Block x

Card 54000 Heat Transfer Calculation Parameters

HTR10_crit.inp* : 54000 0.5 1.0E-5 1000


Word 1 : Semi-implicit weighting factor 0.5

Word 2 : Transient solution convergence criterion 1.0E-5

Word 3 : Max. number of iterations per time step 1000

pebbed6 input manual - catatan studi tsdipura · word 1: sor flux (inner) acceleration parameter (1...

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