26. Cross-section Parameterization Function (Enterprise Version Only)¶
The cross-section parameterization function is developed based on the group constant function, so the relevant input options are included in the group constant module.
26.1. Cross-section Parameterization Module RMC Input Options¶
GroupConstant
ISBURNUPLINE=<Param>
ASSEMBINFO= <univ paras1> < univ paras2> … <univ parasi>
univ parasi = <cell number> <level> <matrix> <rod cell level>
SUBUNIVERSE <Universes>
FORMATTYPE = <Param>
MATINFO = <MatIndexes>
where,
- ISBURNUPLINE is the keyword for information related to statistical cross-section parameterization. The input options can be 0 or 1. 0 means restarting a certain burnup point in the calculation, and 1 means a complete burnup chain (branch) calculation. Note: This option indicates if each area is a burnup zone, so the number of parameters used in the input options later needs to be consistent with the number of universes.
- ASSEMBINFO is a keyword for statistical cross-section parameterization related information, where the input option is a set of data. The number of data sets needs to be consistent with the number of regions defined by the universe input option of the group constant. Each dataset contains 4 different required pieces of data: <cell number> is the number of cells contained in the homogenization assembly. <level> indicates the level of the lattice in the area. <matrix> indicates the assembly shape, that is, the number of rows (the default assembly is a square matrix). <rod cell level> defines the cell level where the rod is located (as the input card has axial stratification, the axial burnup area needs to be accumulated, hence the level of the rod containing the axial stratification needs to be specified). Note: When using the ASSEMBINFO card, the ISBURNUPLINE card must be defined at the same time, otherwise an error will be reported.
- SUBUNIVERSE is an optional input option. For geometries with truncation, input the universe number of the lattice with truncation for each region. For geometries without truncation, input -1. This card can be repeated, but the number of regions must match the number of regions defined on the universe input option for the group constant.
- FORMATTYPE controls the parameterized interface format, where the value of 1 indicates that GAEA format is used, while a value of 2 means that CORCA3D format is being used. Note: The FORMATTYPE input option cannot be placed at the end of the input module, otherwise there will be an error.
- MATINFO requires, in sequence, the material numbers corresponding to the four physical qualities: boron concentration, xenon concentration, moderator density, and fuel temperature.
26.2. Cross-Section Parameterization Module Python Input Options¶
The Python program corresponding to the section parameterization function has two modules. For the parameterization module, an input card needs to be provided, and the file name has to be titled inp_preprocess. inp_preprocess is used to generate the input file of the multi-physics state. The specific format of the file is as follows:
MPI=<para> openmp=<para> platform=<para>
RESTARTBRANCH AUXILIARY
INDEX=<para> MATTEMP=<temperature material> burnuppoint=<para>
In the Python input card:
- MPI/openmp/platform controls computing resources and parallel processing via MPI and openmp. By default, openmp is disabled and MPI=60. Platform sets the computing platform, with the default value being 1, the computing mode as the local server, and the command as: mpiexec -n …; The user can also input the number 2 to indicate that they want to use the Tianhe platform. The command line is: yhrun …
- RESTARTBRANCH/ AUXILIARY_Line represent restart/auxiliary line keywords. Only one option can be chose at a time.
- INDEX represents the branch number.
- MATTEMP represents the material temperature, followed by a specific value (in K), and then the material number that needs to be modified. If all materials need to be modified at the same time, you can input All instead.
- burnuppoint represents the burnup step for restarting the calculation (note: the burnup step number starts from 0, not 1).
The following is a simple example of the Python input card
MPI=80 openmp=12 platform=2
RESTARTBRANCH
INDEX=1 MATTEMP=1000.0 All burnuppoint=0 3 4 6 8 9
INDEX=2 MATTEMP=800.0 All burnuppoint=0 3 4 6 8 9
26.2.1. Example of multi-region model containing hexagonal assemblies¶
The cross-section parameterization function is relatively complex, especially for truncated geometries such as hexagonal assemblies. Therefore, a multi-region model containing hexagonal assemblies is used as an example. The geometry model contains three fuel assemblies, a poison rod assembly, and a reflector layer area at the edge. There are 24 fuel rods inside the fuel assembly, and each rod contains 8 fuel pellets axially. The pellets are filled with fuel particles using the RSA method with a particle packing fraction of 35%. Note: Currently, the RSA model is not considered to have nested layers at the bottom.
图26.3 Multi-region model containing hexagonal assemblies
The figure shown above is a specific geometric model. For the convenience of representation, we have numbered each area of the model, as shown in the figure below.
图26.4 Multi-region model containing hexagonal components (numbered)
The input file example is as follows. Regions 1 to 5 in the geometric model correspond to universes 10, 11, 12, 21, and 13 respectively:
////////////////////// GR5 ////////////////
////////////// sleeve : SiC
////////////// Block bottom graphite, top He(save for future)
///////////// graphite & SiC matrix & sleeve: 1ppm TRISO: 0.5ppm
///////////// top and bottom block, only channels for coolant and CR rod
//Note: Due to the use of burn-up area merging, the volume here represents the total volume of
//all triso particles. This should not have a major impact on burn-up, but the power (rate) will be affected\n
//Each cell requires a given temperature, and the cross-section parameterization here requires
//consistent temperatures\n
Universe 1 //move = 0.050319623 0.050319623 0.050319623 //triso
cell 1 -1 mat = 1 tmp = 1000 vol = 7.5313E-01 //kernel 8.5%
cell 2 1 & -2 mat = 2 tmp = 1000 vol = 1.0422E+00 //buffer
cell 3 2 & -3 mat = 3 tmp = 1000 vol = 6.5565E-01 //IPyC
cell 4 3 & -4 mat = 4 tmp = 1000 vol = 6.9737E-01 //SiC
cell 5 4 & -5 mat = 5 tmp = 1000 vol = 9.5248E-01 //OPyC
cell 6 5 mat = 6 tmp = 1000 vol = 1.0000E-30 //SiC matrix
Universe 2 lat = 4 MATRIC = 3 move = -1.1 -1.1 0.05
PARTICLE = 1
PF = 0.3//0.349631585
RAD = 0.043981974 //PFCORRECT = 0
RSA = 1
TYPE = 2
SIZE = 1.1 3.596
//DEM = 1 TIME = 0.1
Universe 3
cell 14 -6 mat = 6 tmp = 1000
///////// pellet /////
Universe 4
cell 11 -14 & 16 & -19 & !12 mat = 7 tmp = 1000 vol = 1.6864E+00 //sleeve
cell 12 -13 & 17 & -18 fill = 2 vol= 13.6696 //fuel compact
cell 13 14 : -16 : 19 mat = 8 tmp = 1000 vol = 3.4914E-01 //He
Universe 16 // bottom
cell 7 -14 mat = 9 tmp = 1000 vol = 5.9496E+00 //graphite
cell 8 14 mat = 9 tmp = 1000 vol = 1.3527E-01 //graphite
Universe 17 // top
cell 9 -14 mat = 8 tmp = 1000 vol = 1.0000E-30 //He
cell 10 14 mat = 8 tmp = 1000 vol = 1.0000E-30 //He
// 8 pellets
Universe 5 move = 0 0 -2.264 lat = 1 pitch = 1 1 3.696 scope = 1 1 10 fill = 16 4*8 17
Universe 6 // fuel rod
cell 15 -15 fill = 5 vol=131.73 //fuel
cell 16 15 mat = 9 tmp = 1000 vol = 2.9782E+02 //block graphite
Universe 7 //graphite rod
cell 17 -21 mat = 9 tmp = 1000 vol = 4.2955E+02
cell 18 21 mat = 9 tmp = 1000 vol = 1.0000E-30
Universe 8 //coolant rod
cell 19 -20 mat = 8 tmp = 1000 vol = 6.2329E+01 // He
cell 20 20 mat = 9 tmp = 1000 vol = 3.6722E+02 // graphite
Universe 40 //BP1-1
cell 100 -61 & 67 & -68 mat = 15 tmp = 1000 vol = 7.068583
cell 101 61 & -62 & 67 & -68 mat = 15 tmp = 1000 vol = 7.068583
cell 102 62 & -63 & 67 & -68 mat = 15 tmp = 1000 vol = 4.712389
cell 103 63 & -64 & 67 & -68 mat = 15 tmp = 1000 vol = 3.534292
cell 104 64 & -65 & 67 & -68 mat = 15 tmp = 1000 vol = 1.178097
cell 105 ((65 & 67 & -68) : -67 : 68) & -66 mat = 8 tmp = 1000 vol = 5.898340
cell 106 66 mat = 9 tmp = 1000 vol = 185.314015
Universe 41 rotate = -0.5 0.8660254 0 -0.8660254 -0.5 0 0 0 1 //BP1-2 r120
cell 110 -61 & 67 & -68 mat = 15 tmp = 1000 vol = 7.068583
cell 111 61 & -62 & 67 & -68 mat = 15 tmp = 1000 vol = 7.068583
cell 112 62 & -63 & 67 & -68 mat = 15 tmp = 1000 vol = 4.712389
cell 113 63 & -64 & 67 & -68 mat = 15 tmp = 1000 vol = 3.534292
cell 114 64 & -65 & 67 & -68 mat = 15 tmp = 1000 vol = 1.178097
cell 115 ((65 & 67 & -68) : -67 : 68) & -66 mat = 8 tmp = 1000 vol = 5.898340
cell 116 66 mat = 9 tmp = 1000 vol = 185.314015
Universe 42 rotate = -0.5 -0.8660254 0 0.8660254 -0.5 0 0 0 1 //BP1-3 r240
cell 120 -61 & 67 & -68 mat = 15 tmp = 1000 vol = 7.068583
cell 121 61 & -62 & 67 & -68 mat = 15 tmp = 1000 vol = 7.068583
cell 122 62 & -63 & 67 & -68 mat = 15 tmp = 1000 vol = 4.712389
cell 123 63 & -64 & 67 & -68 mat = 15 tmp = 1000 vol = 3.534292
cell 124 64 & -65 & 67 & -68 mat = 15 tmp = 1000 vol = 1.178097
cell 125 ((65 & 67 & -68) : -67 : 68) & -66 mat = 8 tmp = 1000 vol = 5.898340
cell 126 66 mat = 9 tmp = 1000 vol = 185.314015
// block
//The volume of each cell in the lattice is provided on the volume card.\n
Universe 9 move = -24 -13.85640646 0
lat=2 scope= 9 9 sita = 60 pitch = 4 4 fill = //inner block
7 * 9
7 7 7 7 7 6 6 41 7
7 7 7 6 6 8 6 6 7
7 7 6 8 6 6 8 6 7
7 40 6 6 8 6 6 7 7
7 6 8 6 6 8 6 7 7
7 6 6 8 6 6 7 7 7
7 7 6 6 42 7 7 7 7
7 * 9
Universe 10
//The cell volume needs to contain all levels of cells residing in the homogenized area.
//The volume can either be real or relative.\n
cell 27 31 & -32 & -33 & 34 & 35 & -36 fill = 9 vol=498.8452656 //outer block
cell 28 -31 : 32 : 33 : -34 : -35 : 36 mat = 8 tmp = 1000 vol = 8.348729792 //He 1mm
/////// a block end
Universe 11
cell 29 31 & -32 & -33 & 34 & 35 & -36 fill = 9 vol=498.8452656 //outer block
cell 30 -31 : 32 : 33 : -34 : -35 : 36 mat = 8 tmp = 1000 vol = 8.348729792 //He 1mm
Universe 12
cell 31 31 & -32 & -33 & 34 & 35 & -36 fill = 9 vol=498.8452656 //outer block
cell 32 -31 : 32 : 33 : -34 : -35 : 36 mat = 8 tmp = 1000 vol = 8.348729792 //He 1mm
Universe 13
cell 33 -74 mat = 9 tmp = 1000 vol=1.0 //core graphite
Universe 73 //move = 24.2 0 0
cell 60 -40 mat = 8 tmp = 1000 vol=0.188495556//He
cell 61 40 & -41 mat = 12 tmp = 1000 vol=0.146607655//inner cladding
cell 62 41 & -42 mat = 8 tmp = 1000 vol=0.08901179//He
cell 63 42 & -43 mat = 11 tmp = 1000 vol=3.979350627//control rod
cell 64 43 & -44 mat = 8 tmp = 1000 vol=0.184097326//He
cell 65 44 & -45 mat = 12 tmp = 1000 vol=0.64088489//outer cladding
cell 66 45 mat = 8 tmp = 1000 vol=1.939619271//He
Universe 21 //move = 24.2 0 0 ////shutdown contrl column
cell 84 -46 vol=7.168067116 fill = 73
cell 67 46 & 31 & -32 & -33 & 34 & 35 & -36 mat = 9 tmp = 1000 vol=34.40237168 //core graphite
cell 83 -31 : 32 : 33 : -34 : -35 : 36 mat = 8 tmp = 1000 vol=0.695727483 //He 1mm
Universe 30 lat=2 scope= 3 3 sita = 60 pitch = 24.2 24.2 fill = //inner block
13 10 13
21 11 13
12 13 13
Universe 0
cell 90 69 & -70 & 71 & -72 & -73 fill = 30 vol=1.0 //core
cell 92 -69: 70: -71 : 72 : 73 mat = 0 vol=1.0e-30 void = 1
SURFACE
// ----------triso particle
surf 1 so 0.025 // keneral
surf 2 so 0.033396452 // buffer
surf 3 so 0.037047997 // IPyC
surf 4 so 0.040272833 // SiC
surf 5 so 0.043981974 // OPyC
surf 6 inf
/// ----------pellet
//surf 11 cz 0.30 //inner radius
//surf 12 cz 0.35 //outer radius
surf 13 cz 1.1 //pellet
surf 14 cz 1.15 //sleeve radius
surf 15 cz 1.163 //fuel hole
surf 16 pz 0
surf 17 pz 0.05
surf 18 pz 3.646
surf 19 pz 3.696
surf 20 cz 0.8 // coolant hole
/// ---------- block
surf 21 cz 10 // block inner radius
// surf 22 cz 10.05 // inner tube inner radius
// surf 23 cz 10.25 // inner tube outer radius
// surf 24 cz 10.4 // pressure tube inner radius
// surf 25 cz 10.9 // pressure tube outer radius
// surf 26 cz 11 // block outer radius
surf 27 cz 0.75 //relector hole
surf 31 px -12
surf 32 px 12
surf 33 p 1 1.732 0 24
surf 34 p 1 -1.732 0 -24
surf 35 p 1 1.732 0 -24
surf 36 p 1 -1.732 0 24
///----------shutdown control column
surf 40 cz 0.6 //inner clad inside
surf 41 cz 0.8 //inner clad outside
surf 42 cz 0.9 //control rod inside
surf 43 cz 2.9 //control rod outside
surf 44 cz 2.96 //outer clad inside
surf 45 cz 3.16 //outer clad outside
surf 46 cz 3.7 //control rod channel
///------------BP
surf 61 c/z 1 0 0.27386128
surf 62 c/z 1 0 0.38729834
surf 63 c/z 1 0 0.44721360
surf 64 c/z 1 0 0.48733972
surf 65 c/z 1 0 0.5
surf 66 c/z 1 0 0.55
surf 67 pz 0.5
surf 68 pz 30.5
surf 69 pz 0 bc=1
surf 70 pz 31 bc=1
surf 71 px 12.11 bc=1
surf 72 p 1 -1.732 0 24.2 bc=1
surf 73 p 1 1.732 0 96.8 bc=1
surf 74 cz 200
//surf 69 pz 0 bc=1
//surf 70 pz 31 bc=1
//surf 71 px 0 bc=1
//surf 72 px 12.1
//surf 73 p 1 1.732 0 24.2 bc=1
//surf 74 p 1 -1.732 0 -24.2
//surf 75 p 1 1.732 0 -24.2
//surf 76 p 1 -1.732 0 24.2 bc=1
MATERIAL
// -------kernel 8.5%---------
mat 1 -10.4
5010.30c -0.5000E-06
8016.30c -1.1855E-01
8017.30c -5.0406E-05
92234.30c -5.9058E-04
92235.30c -7.4919E-02
92238.30c -8.0589E-01
// ------buffer layer--------
mat 2 -1.235294118
5010.30c 6.8467E-09
6000.30c 6.1936E-02
//sab 2 Graph.71t
// -------IPyC layer---------
mat 3 -2.235294118
5010.30c 1.2389E-08
6000.30c 1.1207E-01
//sab 3 Graph.71t
// -------SiC layer----------
mat 4 -3.741176471
5010.30c 2.0736E-08
6000.30c 5.6189E-02
14028.30c 5.1823E-02
14029.30c 2.6313E-03
14030.30c 1.7346E-03
//sab 4 Graph.71t
// --------OPyC layer--------
mat 5 -2.235294118
5010.30c 1.2389E-08
6000.30c 1.1207E-01
//sab 5 Graph.71t
// ------SiC matrix----
mat 6 -2.933721806
5010.30c 3.2520E-08
6000.30c 4.4062E-02
14028.30c 4.0638E-02
14029.30c 2.0634E-03
14030.30c 1.3602E-03
//sab 6 Graph.71t
// ------SiC sleeve-----
mat 7 -3.18
5010.30c 3.5251E-8
6000.30c 4.7761E-2
14028.30c 4.4050E-2
14029.30c 2.2366E-3
14030.30c 1.4744E-3
//sab 7 Graph.71t
// ------helium coolant------
mat 8 -1.6361E-4
2003.30c 3.3724E-11
2004.30c 2.4616E-5
// ------IG-110 graphite-----
mat 9 -1.7512
5010.30c 1.9412E-8
6000.30c 8.7804E-2
//sab 9 Graph.71t
// ------control rod natural B4C---------
mat 11 -2.5
5010.30c 2.1579E-02
5011.30c 8.7406E-02
6000.30c 2.7246E-02
//sab 11 Graph.71t
// -------alloy 800H---------
mat 12 -8.03
6000.30c 3.2210E-4
13027.30c 6.7209E-4
14028.30c 5.5580E-4
14029.30c 2.8222E-5
14030.30c 1.8604E-5
15031.30c 3.1225E-5
16032.30c 1.4325E-5
16033.30c 1.1311E-7
16034.30c 6.4094E-7
16036.30c 1.5081E-9
22046.30c 3.1254E-5
22047.30c 2.8186E-5
22048.30c 2.7928E-4
22049.30c 2.0495E-5
22050.30c 1.9624E-5
24050.30c 8.4860E-4
24052.30c 1.6364E-2
24053.30c 1.8556E-3
24054.30c 4.6189E-4
25055.30c 8.8022E-4
26054.30c 2.2265E-3
26056.30c 3.4951E-2
26057.30c 8.0717E-4
26058.30c 1.0742E-4
28058.30c 1.8229E-2
28060.30c 7.0217E-3
28061.30c 3.0523E-4
28062.30c 9.7320E-4
28064.30c 2.4785E-4
29063.30c 1.5791E-4
29065.30c 7.0383E-5
// ------ Burnable Poison (Gd2O3 1%) -----
mat 13 -1.71789
5010.30c 1.9043E-8
6000.30c 8.6134E-2
//sab 13 Graph.71t
mat 15 -1.7
6000.30c 8.4383E-02
8016.30c 8.4691E-05
8017.30c 3.3890E-08
64152.30c 1.1297E-07
64154.30c 1.2144E-06
64155.30c 8.3200E-06
64156.30c 1.1562E-05
64157.30c 8.8566E-06
64158.30c 1.4047E-05
64160.30c 1.2370E-05
//sab 15 Graph.71t
CeAce OTFDB=1 OTFSab=0 pTable=0 DBRC=0 ErgBinHash=1
CRITICALITY
PowerIter population = 1000 10 15
InitSrc point = 30 30 5
GroupConstant
//Supports multiple universes. This input option must be placed in the first position
Universe = 10 11 12 13 21
Energy = 4E-6//3.000000E-08 1.463700E-07 3.500000E-07 1.071000E-06 1.855390E-06 9.118820E-03 8.208500E-01
WIMS=0 // Using a two-step method, the WIMS 69 group structure is used. After merging, the energy structure is used. Hence, the energy structure needs to be included in the wims structure\n
BONE=0 //b1 correction is used\n
Hybrid=1 // Output MCNP format multi-group file
Angular=1 //Angular distribution variable order 1 for the default, as p1\n
//Homogenization method，0：Non-Homogenization method，1：DF，2：sph
//DF Parameter：1（quadrilateral) 2（hexagon）
//SPH Parameter：Number of iterations\n
EQUIVALENCE = 2 10
//volume input option description：
//Note: This input option can be defined multiple times, but it needs to be consistent with the input number of universe cards.\n
//The order given by the input options corresponds to the universe of the universe card.
//Volume input option contains 5 lines of data
//The first data in the first line is the total volume (real volume), used for sph calculation\n
//1-3 //4-5 //6-7 //8-9 //axial
volume = 7732 0*20 71.59 0*6
0*2 4.2955E+02 2.1477E+02 0*6 2.1477E+02 4.2955E+02*2 2.1477E+02 0*4
0 4.2955E+02*4 2.1477E+02 0*3 1.4318E+02 4.2955E+02*5 71.59 0*2
0 2.1477E+02 4.2955E+02*2 2.1477E+02 0*6 1.4318E+02 0*6
0 3.696*8 1.432
volume = 1.5464E+04 1.0E-30*6 1.4318E+02 1.0E-30*6 2.1477E+02 4.2955E+02*2 2.1477E+02 1.0E-30*3 1.4318E+02 4.2955E+02*5 1.4318E+02
1.0E-30*2 4.2955E+02*6 1.0E-30*2 2.1477E+02 4.2955E+02*5 2.1477E+02 1.0E-30*2 4.2955E+02*6 1.0E-30*2
1.4318E+02 4.2955E+02*5 1.4318E+02 1.0E-30*3 2.1477E+02 4.2955E+02*2 2.1477E+02 1.0E-30*6 1.4318E+02
1.0E-30*6 0 3.696*8 1.432
//Volume input option contains 5 lines of data
//The first data in the first line is the total volume (real volume), used for sph calculation\n
//81 data structures：
//1-2 //3-4 //5-6 //7-9
//10 axial data
//Note: Do not add comments inside the volume input option. If there is too much data, you can write the data in separate lines.\n
volume = 7732 0*6 1.4318E+02 0*6 2.1477E+02 4.2955E+02*2 2.1477E+02 0
0*2 1.4318E+02 4.2955E+02*5 71.59 0*2 4.2955E+02*4 2.1477E+02 0*2
0 2.1477E+02 4.2955E+02*2 2.1477E+02 0*5 4.2955E+02 2.1477E+02 0*6
71.59 0*26
0 3.696*8 1.432
//Corresponding to universe 13, this area is not a lattice, hence a value of 1.0 is sufficient\n
//But if you wish to calculate SPH and produce the real volume\n
volume = 2577.3
//Corresponding to universe 21, this area is not a lattice, hence a value of 1.0 is sufficient\n
volume = 7732
//ASSEMBINFO input option description：
//Structure: <univ paras>...
//<cell number>,<level>,<matrix>,<axial para num>,<axial para>
//Meaning:
//The number of universes = number of sets of <univ paras> data to be provided
//Each set of <univ paras> includes <cell number>,<level>,<matrix>,<rod cell level>
//For example, universe10 contains 81 1 9 16 8 1*15
//Universe10 includes 81 cells,lattice structure. As per the hierarchy, we go down 1 layer, find universe9,
//and output the h5 file of the power and fuel consumption of this area. The 9*9 matrix is used to output 81 sets of data.\n
//Since the input card has axial stratification, the axial burnup area has to be accumulated, so this card is set up
//The burncell in universe10 contains: 1 100 101 102 103 104 110 111 112 113 114 120 121 122 123 124
//Since the input card is divided into axial directions according to the cell vector, the meaning of 3 is: 90 > 2 > 27 > 15, (0, 1, 2, 3)
ASSEMBINFO = 81 1 9 3 81 1 9 3 81 1 9 3 1 0 1 3 1 0 1 3
////Branch signal
//A value of 1 means main line, auxiliary line, while 2 means to restart\n
ISBURNUPLINE 1
//Input whether each area is a fuel consumption area, 1 is yes, 0 is no
IsBurnRegion=1 1 1 0 0
//SUBUNIVERSE：
//Repeated definition of this input option is supported
//For geometric cutoff cases\n
//The order in which the input options are provided corresponds to the universe of the universe card
//Using universe10 as an example: There are two truncated areas, 9 and 5 (the volume input gives 9 first, then 5)\n
SUBUNIVERSE=9 5
SUBUNIVERSE=9 5
SUBUNIVERSE=9 5
//If there is no truncation or if truncation has no effect, -1 is given.
SUBUNIVERSE=-1
SUBUNIVERSE=-1
FORMATTYPE = 1
//Input Option for setting status parameters
//Boron concentration, xenon concentration, moderator density, fuel temperature vs. material number\n
MATINFO = 9 1 9 1
//Note: Cutting off the burn-up area will result in a 0 energy warning, which does not affect the calculation\n
//Consider replacing the truncated burnup area with a non-burnup structure instead\n
BURNUP
BurnCell 1 100 101 102 103 104 110 111 112 113 114 120 121 122 123 124
TimeStep 10 20//
Power 17.98162286*2
Substep 10
Inherent 0.9999
AceLib .30c
Strategy 0
Parallel 1
Solver 2
Merge 7 2 //burnup zone merging function, (level /universe) 0->30->10/11/12->9->6->5->4->2 (7 layers), note that 10, 11, 12 must be on the same layer, otherwise an error will occur\n
//Plot ColorScheme=9 Continue-calculation=0
//PlotID 1 Type = slice Color = mat Pixels=5000 5000 Vertexes=10 -8 5 60.5 60 5
//PlotID 2 Type = slice Color = mat Pixels=4000 4000 Vertexes= 20 -8 -1 20 60 32
//PlotID 3 Type = slice Color = cell Pixels=4000 8000 Vertexes=23 -1 5 24 1 5
26.3. Parameterized Calculation Description¶
The calculation process of cross-section parameterization is as follows:
Before using Python for calculation, please make sure that you have used RMC to complete the group constant calculation. The group constant calculation requires turning on options such as EQUIVALENCE = 2 and Hybrid = 1. For details, see the RMC user manual for the group constant module description. When calculating the group constant, be sure to turn on the continuation calculation function (in the output control module, define inpfile as 1) for restarting the calculation of cross-section parameterization.
Calculation Process:
Prepare inp_preprocess for auxiliary line, restart and other calculations;
Prepare RMC program, xsdir and other files and programs
Prepare the subsequent output files (XXX.FMTinp.stepXXX and materialXX)
Run main.py to complete the construction and calculation of parameterized branch files
Use the RMC input file and multi-group output file generated by the branch to perform SPH calculations in the Python program folder of SPH. Note that the restarted SPH file is processed by Python (path: ~/Restart/branch_xx/xsparatable_SPH.h5)
Copy the sph calculation result file
Each sph_Iter.h5 of the auxiliary line is placed in ~/Auxliary/branch_xx/burnup_xx/
Each sph_Iter.h5 of the main line is placed in ~/burnup_xx/
Each sph_Iter.h5 that is restarted is placed in ~/Restart/branch_xx/step_xx/
Restart and delete the ~/Restart/branch_xx/xsparatable_SPH.h5 file
Prepare the Pair_inp file, which sets the correspondence between the parameterized area and the sph area
Run ChangeRestartXS.py and ChangeAuxliaryXS.py
Run H5FileFormat.py
The final result is in the Result folder