HEU-MET-FAST-001

Input

set title "Godiva solid bare HEU sphere. CSB Data used. 05/12/93."

cell 1 0 m1 -1
cell 2 0 outside 1

surf 1 sph 0.0 0.0 0.0 8.7407

mat m1 4.7984E-02
92235.03c 4.4994E-02 
92238.03c 2.4984E-03 
92234.03c 4.9184E-04

set pop 200000 500 20
set acelib "sss_endfb7u.xsdata"
set ures 1

Output

% Increase counter:

if (exist('idx', 'var'));
  idx = idx + 1;
else;
  idx = 1;
end;

% Version, title and date:

VERSION                   (idx, [1: 14])  = 'Serpent 2.1.24' ;
COMPILE_DATE              (idx, [1: 20])  = 'Jun 25 2015 16:26:43' ;
DEBUG                     (idx, 1)        = 0 ;
TITLE                     (idx, [1: 54])  = 'Godiva solid bare HEU sphere. CSB Data used. 05/12/93.' ;
INPUT_FILE_NAME           (idx, [1: 16])  = 'HEU-MET-FAST-001' ;
WORKING_DIRECTORY         (idx, [1: 59])  = '/data/projects/super/timeconstants/Rossi_benchmark/Serpent2' ;
HOSTNAME                  (idx, [1: 10])  = 'ESPTT3M111' ;
CPU_TYPE                  (idx, [1: 47])  = 'Intel(R) Xeon(R) CPU           X5690  @ 3.47GHz' ;
CPU_MHZ                   (idx, 1)        = 3459.0 ;
START_DATE                (idx, [1: 24])  = 'Wed Nov 18 15:38:47 2015' ;
COMPLETE_DATE             (idx, [1: 24])  = 'Wed Nov 18 15:43:32 2015' ;

% Run parameters:

POP                       (idx, 1)        = 200000 ;
CYCLES                    (idx, 1)        = 500 ;
SKIP                      (idx, 1)        = 20 ;
BATCH_INTERVAL            (idx, 1)        = 1 ;
SRC_NORM_MODE             (idx, 1)        = 2 ;
SEED                      (idx, 1)        = 1447853927 ;
UFS_MODE                  (idx, 1)        = 0 ;
UFS_ORDER                 (idx, 1)        = 1.00000;
NEUTRON_TRANSPORT_MODE    (idx, 1)        = 1 ;
PHOTON_TRANSPORT_MODE     (idx, 1)        = 0 ;
GROUP_CONSTANT_GENERATION (idx, 1)        = 1 ;
B1_CALCULATION            (idx, [1:  3])  = [ 0 0 0 ];
B1_BURNUP_CORRECTION      (idx, 1)        = 0 ;
IMPLICIT_REACTION_RATES   (idx, 1)        = 1 ;

% Optimization:

OPTIMIZATION_MODE         (idx, 1)        = 4 ;
RECONSTRUCT_MICROXS       (idx, 1)        = 1 ;
RECONSTRUCT_MACROXS       (idx, 1)        = 1 ;
MG_MAJORANT_MODE          (idx, 1)        = 0 ;

% Parallelization:

MPI_TASKS                 (idx, 1)        = 1 ;
OMP_THREADS               (idx, 1)        = 24 ;
MPI_REPRODUCIBILITY       (idx, 1)        = 0 ;
OMP_REPRODUCIBILITY       (idx, 1)        = 1 ;
OMP_HISTORY_PROFILE       (idx, [1:  24]) = [  1.02421E+00  9.79344E-01  9.80398E-01  1.02266E+00  9.68984E-01  1.02009E+00  9.76365E-01  1.02755E+00  1.03283E+00  9.79792E-01  1.02170E+00  9.73811E-01  1.02125E+00  9.73769E-01  1.02891E+00  1.00042E+00  1.02927E+00  9.76937E-01  9.99120E-01  9.73825E-01  1.00867E+00  9.78984E-01  1.02300E+00  9.78080E-01  ];
SHARE_BUF_ARRAY           (idx, 1)        = 0 ;
SHARE_RES2_ARRAY          (idx, 1)        = 1 ;

% File paths:

XS_DATA_FILE_PATH         (idx, [1: 22])  = '/xs/sss_endfb7u.xsdata' ;
DECAY_DATA_FILE_PATH      (idx, [1:  3])  = 'N/A' ;
SFY_DATA_FILE_PATH        (idx, [1:  3])  = 'N/A' ;
NFY_DATA_FILE_PATH        (idx, [1:  3])  = 'N/A' ;
BRA_DATA_FILE_PATH        (idx, [1:  3])  = 'N/A' ;

% Collision and reaction sampling (neutrons/photons):

MIN_MACROXS               (idx, [1:   4]) = [  2.74533E-01 0.0E+00  0.00000E+00 0.0E+00 ];
DT_THRESH                 (idx, [1:  2])  = [  9.00000E-01  9.00000E-01 ];
ST_FRAC                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
DT_FRAC                   (idx, [1:   4]) = [  1.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
DT_EFF                    (idx, [1:   4]) = [  9.92052E-01 8.3E-06  0.00000E+00 0.0E+00 ];
REA_SAMPLING_EFF          (idx, [1:   4]) = [  1.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
REA_SAMPLING_FAIL         (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
TOT_COL_EFF               (idx, [1:   4]) = [  9.92052E-01 8.3E-06  0.00000E+00 0.0E+00 ];
AVG_TRACKING_LOOPS        (idx, [1:   8]) = [  1.69359E+00 2.9E-05  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
AVG_TRACKS                (idx, [1:   4]) = [  3.20962E+00 9.2E-05  0.00000E+00 0.0E+00 ];
AVG_REAL_COL              (idx, [1:   4]) = [  2.63810E+00 0.00011  0.00000E+00 0.0E+00 ];
AVG_VIRT_COL              (idx, [1:   4]) = [  2.11346E-02 0.00106  0.00000E+00 0.0E+00 ];
AVG_SURF_CROSS            (idx, [1:   4]) = [  5.71518E-01 8.6E-05  0.00000E+00 0.0E+00 ];

% Run statistics:

CYCLE_IDX                 (idx, 1)        = 500 ;
SOURCE_POPULATION         (idx, 1)        = 100002091 ;
MEAN_POP_SIZE             (idx, [1:  2])  = [  2.00004E+05 0.00018 ];
MEAN_POP_WGT              (idx, [1:  2])  = [  2.00004E+05 0.00018 ];
SIMULATION_COMPLETED      (idx, 1)        = 1 ;

% Running times:

TOT_CPU_TIME              (idx, 1)        =  5.02430E+01 ;
RUNNING_TIME              (idx, 1)        =  4.74358E+00 ;
INIT_TIME                 (idx, [1:  2])  = [  3.25667E-02  3.25667E-02 ];
PROCESS_TIME              (idx, [1:  2])  = [  4.66667E-04  4.66667E-04 ];
TRANSPORT_CYCLE_TIME      (idx, [1:  3])  = [  4.71055E+00  4.71055E+00  0.00000E+00 ];
MPI_OVERHEAD_TIME         (idx, [1:  2])  = [  0.00000E+00  0.00000E+00 ];
ESTIMATED_RUNNING_TIME    (idx, [1:  2])  = [  4.74310E+00  0.00000E+00 ];
CPU_USAGE                 (idx, 1)        = 10.59178 ;
TRANSPORT_CPU_USAGE       (idx, [1:   2]) = [  1.06045E+01 0.00028 ];
OMP_PARALLEL_FRAC         (idx, 1)        =  4.14669E-01 ;

% Memory usage:

AVAIL_MEM                 (idx, 1)        = 96873.23 ;
ALLOC_MEMSIZE             (idx, 1)        = 6965.73;
MEMSIZE                   (idx, 1)        = 1221.43;
XS_MEMSIZE                (idx, 1)        = 68.44;
MAT_MEMSIZE               (idx, 1)        = 6.46;
RES_MEMSIZE               (idx, 1)        = 1.47;
MISC_MEMSIZE              (idx, 1)        = 1145.06;
UNKNOWN_MEMSIZE           (idx, 1)        = 0.00;
UNUSED_MEMSIZE            (idx, 1)        = 5744.30;

% Geometry parameters:

TOT_CELLS                 (idx, 1)        = 2 ;
UNION_CELLS               (idx, 1)        = 0 ;

% Neutron energy grid:

NEUTRON_ERG_TOL           (idx, 1)        =  0.00000E+00 ;
NEUTRON_ERG_NE            (idx, 1)        = 105371 ;
NEUTRON_EMIN              (idx, 1)        =  1.00000E-11 ;
NEUTRON_EMAX              (idx, 1)        =  2.00000E+01 ;

% Unresolved resonance probability table sampling:

URES_DILU_CUT             (idx, 1)        =  1.00000E-09 ;
URES_EMIN                 (idx, 1)        =  1.50000E-03 ;
URES_EMAX                 (idx, 1)        =  1.49029E-01 ;
URES_AVAIL                (idx, 1)        = 3 ;
URES_USED                 (idx, 1)        = 3 ;

% Nuclides and reaction channels:

TOT_NUCLIDES              (idx, 1)        = 3 ;
TOT_TRANSPORT_NUCLIDES    (idx, 1)        = 3 ;
TOT_DOSIMETRY_NUCLIDES    (idx, 1)        = 0 ;
TOT_DECAY_NUCLIDES        (idx, 1)        = 0 ;
TOT_PHOTON_NUCLIDES       (idx, 1)        = 0 ;
TOT_REA_CHANNELS          (idx, 1)        = 144 ;
TOT_TRANSMU_REA           (idx, 1)        = 0 ;

% Neutron physics options:

USE_DELNU                 (idx, 1)        = 1 ;
USE_URES                  (idx, 1)        = 1 ;
USE_DBRC                  (idx, 1)        = 0 ;
IMPL_CAPT                 (idx, 1)        = 0 ;
IMPL_NXN                  (idx, 1)        = 1 ;
IMPL_FISS                 (idx, 1)        = 0 ;
DOPPLER_PREPROCESSOR      (idx, 1)        = 0 ;
TMS_MODE                  (idx, 1)        = 0 ;
SAMPLE_FISS               (idx, 1)        = 1 ;
SAMPLE_CAPT               (idx, 1)        = 1 ;
SAMPLE_SCATT              (idx, 1)        = 1 ;

% Radioactivity data:

TOT_ACTIVITY              (idx, 1)        =  0.00000E+00 ;
TOT_DECAY_HEAT            (idx, 1)        =  0.00000E+00 ;
TOT_SF_RATE               (idx, 1)        =  0.00000E+00 ;
ACTINIDE_ACTIVITY         (idx, 1)        =  0.00000E+00 ;
ACTINIDE_DECAY_HEAT       (idx, 1)        =  0.00000E+00 ;
FISSION_PRODUCT_ACTIVITY  (idx, 1)        =  0.00000E+00 ;
FISSION_PRODUCT_DECAY_HEAT(idx, 1)        =  0.00000E+00 ;
INHALATION_TOXICITY       (idx, 1)        =  0.00000E+00 ;
INGESTION_TOXICITY        (idx, 1)        =  0.00000E+00 ;
SR90_ACTIVITY             (idx, 1)        =  0.00000E+00 ;
TE132_ACTIVITY            (idx, 1)        =  0.00000E+00 ;
I131_ACTIVITY             (idx, 1)        =  0.00000E+00 ;
I132_ACTIVITY             (idx, 1)        =  0.00000E+00 ;
CS134_ACTIVITY            (idx, 1)        =  0.00000E+00 ;
CS137_ACTIVITY            (idx, 1)        =  0.00000E+00 ;
TOT_PHOTON_SRC            (idx, 1)        =  0.00000E+00 ;

% Normaliation coefficient:

NORM_COEF                 (idx, [1:   4]) = [  4.98729E-06 6.1E-05  0.00000E+00 0.0E+00 ];

% Analog reaction rate estimators:

CONVERSION_RATIO          (idx, [1:   2]) = [  3.71085E-03 0.00258 ];
U235_FISS                 (idx, [1:   4]) = [  3.77228E-01 0.00018  9.83103E-01 2.0E-05 ];
U238_FISS                 (idx, [1:   4]) = [  3.36185E-03 0.00159  8.76148E-03 0.00159 ];
U235_CAPT                 (idx, [1:   4]) = [  4.28694E-02 0.00047  9.55657E-01 0.00010 ];
U238_CAPT                 (idx, [1:   4]) = [  1.55887E-03 0.00256  3.47504E-02 0.00251 ];

% Normalized total reaction rates (neutrons):

TOT_POWER                 (idx, [1:   2]) = [  1.24225E-11 8.4E-05 ];
TOT_POWDENS               (idx, [1:   2]) = [  2.36980E-19 8.4E-05 ];
TOT_GENRATE               (idx, [1:   2]) = [  9.97282E-01 8.3E-05 ];
TOT_FISSRATE              (idx, [1:   2]) = [  3.83743E-01 8.4E-05 ];
TOT_CAPTRATE              (idx, [1:   2]) = [  4.48258E-02 0.00014 ];
TOT_ABSRATE               (idx, [1:   2]) = [  4.28568E-01 8.7E-05 ];
TOT_SRCRATE               (idx, [1:   2]) = [  9.97459E-01 6.1E-05 ];
TOT_FLUX                  (idx, [1:   2]) = [  6.75778E+00 8.4E-05 ];
TOT_LEAKRATE              (idx, [1:   2]) = [  5.71432E-01 6.5E-05 ];
ALBEDO_LEAKRATE           (idx, [1:   2]) = [  0.00000E+00 0.0E+00 ];
TOT_LOSSRATE              (idx, [1:   2]) = [  1.00000E+00 0.0E+00 ];
TOT_CUTRATE               (idx, [1:   2]) = [  0.00000E+00 0.0E+00 ];
TOT_RR                    (idx, [1:   2]) = [  2.63883E+00 9.0E-05 ];
INI_FMASS                 (idx, 1)        =  5.24202E+01 ;
TOT_FMASS                 (idx, 1)        =  5.24202E+01 ;

% Fission neutron and energy production:

NUBAR                     (idx, [1:   2]) = [  2.59883E+00 8.7E-06 ];
FISSE                     (idx, [1:   2]) = [  2.02051E+02 2.5E-08 ];

% Criticality eigenvalues:

ANA_KEFF                  (idx, [1:   6]) = [  9.99744E-01 0.00013  9.93308E-01 0.00013  6.44533E-03 0.00194 ];
IMP_KEFF                  (idx, [1:   2]) = [  9.99828E-01 8.4E-05 ];
COL_KEFF                  (idx, [1:   2]) = [  9.99825E-01 0.00010 ];
ABS_KEFF                  (idx, [1:   2]) = [  9.99828E-01 8.4E-05 ];
ABS_KINF                  (idx, [1:   2]) = [  2.34092E+00 2.0E-05 ];
GEOM_ALBEDO               (idx, [1:   6]) = [  1.00000E+00 0.0E+00  1.00000E+00 0.0E+00  1.00000E+00 0.0E+00 ];

% Forward-weighted delayed neutron parameters:

FWD_ANA_BETA_ZERO         (idx, [1:  14]) = [  6.44906E-03 0.00132  2.02365E-04 0.00690  1.06736E-03 0.00302  1.03374E-03 0.00307  2.96518E-03 0.00184  8.74528E-04 0.00355  3.05878E-04 0.00588 ];
FWD_ANA_LAMBDA            (idx, [1:  14]) = [  7.64050E-01 0.00300  1.24905E-02 5.4E-07  3.17953E-02 2.1E-05  1.09479E-01 2.6E-05  3.17452E-01 2.3E-05  1.35230E+00 2.1E-05  8.67734E+00 0.00016 ];

% Beta-eff using Meulekamp's method:

ADJ_MEULEKAMP_BETA_EFF    (idx, [1:  14]) = [  6.75228E-03 0.00171  2.15226E-04 0.00998  1.12083E-03 0.00417  1.09111E-03 0.00427  3.07769E-03 0.00247  9.21188E-04 0.00502  3.26246E-04 0.00832 ];
ADJ_MEULEKAMP_LAMBDA      (idx, [1:  14]) = [  7.71596E-01 0.00431  1.24905E-02 7.5E-07  3.17955E-02 2.9E-05  1.09474E-01 3.4E-05  3.17455E-01 3.2E-05  1.35229E+00 2.9E-05  8.67573E+00 0.00021 ];

% Adjoint weighted time constants using Nauchi's method:

ADJ_NAUCHI_GEN_TIME       (idx, [1:   6]) = [  5.70737E-09 0.00035  5.67805E-09 0.00035  1.01972E-08 0.00351 ];
ADJ_NAUCHI_LIFETIME       (idx, [1:   6]) = [  5.70585E-09 0.00032  5.67654E-09 0.00033  1.01945E-08 0.00350 ];
ADJ_NAUCHI_BETA_EFF       (idx, [1:  14]) = [  6.44655E-03 0.00195  2.07668E-04 0.01082  1.06612E-03 0.00462  1.03682E-03 0.00485  2.94216E-03 0.00285  8.84832E-04 0.00546  3.08949E-04 0.00954 ];
ADJ_NAUCHI_LAMBDA         (idx, [1:  14]) = [  7.69170E-01 0.00486  1.24905E-02 9.0E-07  3.17958E-02 3.0E-05  1.09479E-01 4.1E-05  3.17452E-01 3.5E-05  1.35227E+00 3.5E-05  8.67345E+00 0.00024 ];

% Adjoint weighted time constants using IFP:

ADJ_IFP_GEN_TIME          (idx, [1:   6]) = [  5.69285E-09 0.00087  5.66311E-09 0.00088  1.02439E-08 0.00983 ];
ADJ_IFP_LIFETIME          (idx, [1:   6]) = [  5.69135E-09 0.00087  5.66162E-09 0.00087  1.02414E-08 0.00983 ];
ADJ_IFP_IMP_BETA_EFF      (idx, [1:  14]) = [  6.51739E-03 0.00684  2.12695E-04 0.03984  1.09400E-03 0.01646  1.05684E-03 0.01665  2.95393E-03 0.00989  8.91352E-04 0.01853  3.08574E-04 0.03324 ];
ADJ_IFP_IMP_LAMBDA        (idx, [1:  14]) = [  7.61773E-01 0.01703  1.24905E-02 3.1E-06  3.17964E-02 9.6E-05  1.09463E-01 0.00012  3.17510E-01 0.00013  1.35238E+00 0.00010  8.66713E+00 0.00076 ];
ADJ_IFP_ANA_BETA_EFF      (idx, [1:  14]) = [  6.49875E-03 0.00671  2.10802E-04 0.03929  1.08772E-03 0.01615  1.04928E-03 0.01615  2.95229E-03 0.00973  8.91768E-04 0.01832  3.06888E-04 0.03227 ];
ADJ_IFP_ANA_LAMBDA        (idx, [1:  14]) = [  7.61899E-01 0.01654  1.24905E-02 2.9E-06  3.17978E-02 9.0E-05  1.09461E-01 0.00012  3.17506E-01 0.00012  1.35238E+00 0.00010  8.66844E+00 0.00080 ];
ADJ_IFP_ROSSI_ALPHA       (idx, [1:   2]) = [ -1.15138E+06 0.00691 ];

% Adjoint weighted time constants using perturbation technique:

ADJ_PERT_GEN_TIME         (idx, [1:   2]) = [  5.70912E-09 0.00019 ];
ADJ_PERT_LIFETIME         (idx, [1:   2]) = [  5.70763E-09 0.00018 ];
ADJ_PERT_BETA_EFF         (idx, [1:   2]) = [  6.51997E-03 0.00139 ];
ADJ_PERT_ROSSI_ALPHA      (idx, [1:   2]) = [ -1.14202E+06 0.00137 ];

% Inverse neutron speed :

ANA_INV_SPD               (idx, [1:   2]) = [  9.22997E-10 8.6E-05 ];

% Analog slowing-down and thermal neutron lifetime (total/prompt/delayed):

ANA_SLOW_TIME             (idx, [1:   6]) = [  5.68506E-12 1.00000  5.68506E-12 1.00000  0.00000E+00 0.0E+00 ];
ANA_THERM_TIME            (idx, [1:   6]) = [  5.07290E-10 1.00000  5.07290E-10 1.00000  0.00000E+00 0.0E+00 ];
ANA_THERM_FRAC            (idx, [1:   6]) = [  9.95887E-09 1.00000 -1.99420E-11 1.00000  0.00000E+00 0.0E+00 ];
ANA_DELAYED_EMTIME        (idx, [1:   2]) = [  1.07500E+01 0.00285 ];

% Group constant generation:

GC_UNIVERSE_NAME          (idx, [1:  1])  = '0' ;

% Micro- and macro-group structures:

MICRO_NG                  (idx, 1)        = 70 ;
MICRO_E                   (idx, [1:  71]) = [  2.00000E+01  6.06550E+00  3.67900E+00  2.23100E+00  1.35300E+00  8.21000E-01  5.00000E-01  3.02500E-01  1.83000E-01  1.11000E-01  6.74300E-02  4.08500E-02  2.47800E-02  1.50300E-02  9.11800E-03  5.50000E-03  3.51910E-03  2.23945E-03  1.42510E-03  9.06898E-04  3.67262E-04  1.48728E-04  7.55014E-05  4.80520E-05  2.77000E-05  1.59680E-05  9.87700E-06  4.00000E-06  3.30000E-06  2.60000E-06  2.10000E-06  1.85500E-06  1.50000E-06  1.30000E-06  1.15000E-06  1.12300E-06  1.09700E-06  1.07100E-06  1.04500E-06  1.02000E-06  9.96000E-07  9.72000E-07  9.50000E-07  9.10000E-07  8.50000E-07  7.80000E-07  6.25000E-07  5.00000E-07  4.00000E-07  3.50000E-07  3.20000E-07  3.00000E-07  2.80000E-07  2.50000E-07  2.20000E-07  1.80000E-07  1.40000E-07  1.00000E-07  8.00000E-08  6.70000E-08  5.80000E-08  5.00000E-08  4.20000E-08  3.50000E-08  3.00000E-08  2.50000E-08  2.00000E-08  1.50000E-08  1.00000E-08  5.00000E-09  1.00000E-11 ];

MACRO_NG                  (idx, 1)        = 2 ;
MACRO_E                   (idx, [1:   3]) = [  1.00000E+37  6.25000E-07  0.00000E+00 ];

% Integral parameters:

INF_KINF                  (idx, [1:   2]) = [  2.34090E+00 0.00013 ];

% Flux spectrum in infinite geometry:

INF_FLX                   (idx, [1:   4]) = [  6.75780E+00 8.3E-05  1.25534E-09 1.00000 ];

% Reaction cross sections:

INF_TOT                   (idx, [1:   4]) = [  3.90487E-01 2.3E-05  7.91650E+00 0.0E+00 ];
INF_CAPT                  (idx, [1:   4]) = [  6.63322E-03 9.9E-05  1.09803E+00 0.0E+00 ];
INF_ABS                   (idx, [1:   4]) = [  6.34185E-02 1.9E-05  7.24461E+00 0.0E+00 ];
INF_FISS                  (idx, [1:   4]) = [  5.67853E-02 1.2E-05  6.14658E+00 0.0E+00 ];
INF_NSF                   (idx, [1:   4]) = [  1.47575E-01 1.6E-05  1.49774E+01 0.0E+00 ];
INF_NUBAR                 (idx, [1:   4]) = [  2.59883E+00 7.8E-06  2.43670E+00 0.0E+00 ];
INF_KAPPA                 (idx, [1:   4]) = [  2.02051E+02 2.4E-08  2.02023E+02 0.0E+00 ];
INF_INVV                  (idx, [1:   4]) = [  9.22998E-10 7.6E-05  1.19036E-06 0.0E+00 ];

% Total scattering cross sections:

INF_SCATT0                (idx, [1:   4]) = [  3.27068E-01 4.6E-05  0.00000E+00 0.0E+00 ];
INF_SCATT1                (idx, [1:   4]) = [  1.07478E-01 0.00011  0.00000E+00 0.0E+00 ];
INF_SCATT2                (idx, [1:   4]) = [  5.84654E-02 0.00021  0.00000E+00 0.0E+00 ];
INF_SCATT3                (idx, [1:   4]) = [  3.97255E-02 0.00020  0.00000E+00 0.0E+00 ];
INF_SCATT4                (idx, [1:   4]) = [  2.57735E-02 0.00035  0.00000E+00 0.0E+00 ];
INF_SCATT5                (idx, [1:   4]) = [  1.38318E-02 0.00053  0.00000E+00 0.0E+00 ];
INF_SCATT6                (idx, [1:   4]) = [  7.17023E-03 0.00103  0.00000E+00 0.0E+00 ];
INF_SCATT7                (idx, [1:   4]) = [  3.15862E-03 0.00186  0.00000E+00 0.0E+00 ];

% Total scattering production cross sections:

INF_SCATTP0               (idx, [1:   4]) = [  3.27445E-01 4.6E-05  0.00000E+00 0.0E+00 ];
INF_SCATTP1               (idx, [1:   4]) = [  1.07484E-01 0.00011  0.00000E+00 0.0E+00 ];
INF_SCATTP2               (idx, [1:   4]) = [  5.84671E-02 0.00021  0.00000E+00 0.0E+00 ];
INF_SCATTP3               (idx, [1:   4]) = [  3.97259E-02 0.00020  0.00000E+00 0.0E+00 ];
INF_SCATTP4               (idx, [1:   4]) = [  2.57734E-02 0.00035  0.00000E+00 0.0E+00 ];
INF_SCATTP5               (idx, [1:   4]) = [  1.38319E-02 0.00053  0.00000E+00 0.0E+00 ];
INF_SCATTP6               (idx, [1:   4]) = [  7.16999E-03 0.00103  0.00000E+00 0.0E+00 ];
INF_SCATTP7               (idx, [1:   4]) = [  3.15849E-03 0.00186  0.00000E+00 0.0E+00 ];

% Diffusion parameters:

INF_TRANSPXS              (idx, [1:   4]) = [  2.61424E-01 5.2E-05  0.00000E+00 0.0E+00 ];
INF_DIFFCOEF              (idx, [1:   4]) = [  1.27507E+00 5.2E-05  0.00000E+00 0.0E+00 ];

% Reduced absoption and removal:

INF_RABSXS                (idx, [1:   4]) = [  6.30422E-02 1.9E-05  7.24461E+00 0.0E+00 ];
INF_REMXS                 (idx, [1:   4]) = [  6.34185E-02 0.00013  7.91650E+00 0.0E+00 ];

% Poison cross sections:

INF_I135_YIELD            (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_XE135_YIELD           (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_PM149_YIELD           (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SM149_YIELD           (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_I135_MICRO_ABS        (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_XE135_MICRO_ABS       (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_PM149_MICRO_ABS       (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SM149_MICRO_ABS       (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_XE135_MACRO_ABS       (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SM149_MACRO_ABS       (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Fission spectra:

INF_CHIT                  (idx, [1:   4]) = [  1.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_CHIP                  (idx, [1:   4]) = [  1.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_CHID                  (idx, [1:   4]) = [  1.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Scattering matrixes:

INF_S0                    (idx, [1:   8]) = [  3.27068E-01 4.6E-05  1.47034E-09 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S1                    (idx, [1:   8]) = [  1.07478E-01 0.00011  6.94726E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S2                    (idx, [1:   8]) = [  5.84654E-02 0.00021 -2.42790E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S3                    (idx, [1:   8]) = [  3.97255E-02 0.00020 -6.54345E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S4                    (idx, [1:   8]) = [  2.57735E-02 0.00035 -3.58961E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S5                    (idx, [1:   8]) = [  1.38318E-02 0.00053  2.18184E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S6                    (idx, [1:   8]) = [  7.17023E-03 0.00103  4.88133E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_S7                    (idx, [1:   8]) = [  3.15862E-03 0.00186  2.41316E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Scattering production matrixes:

INF_SP0                   (idx, [1:   8]) = [  3.27445E-01 4.6E-05  1.47034E-09 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP1                   (idx, [1:   8]) = [  1.07484E-01 0.00011  6.94726E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP2                   (idx, [1:   8]) = [  5.84671E-02 0.00021 -2.42790E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP3                   (idx, [1:   8]) = [  3.97259E-02 0.00020 -6.54345E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP4                   (idx, [1:   8]) = [  2.57734E-02 0.00035 -3.58961E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP5                   (idx, [1:   8]) = [  1.38319E-02 0.00053  2.18184E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP6                   (idx, [1:   8]) = [  7.16999E-03 0.00103  4.88133E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
INF_SP7                   (idx, [1:   8]) = [  3.15849E-03 0.00186  2.41316E-10 1.00000  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Integral parameters:

B1_KINF                   (idx, [1:   2]) = [  0.00000E+00 0.0E+00 ];
B1_KEFF                   (idx, [1:   2]) = [  0.00000E+00 0.0E+00 ];
B1_B2                     (idx, [1:   2]) = [  0.00000E+00 0.0E+00 ];
B1_ERR                    (idx, [1:   2]) = [  0.00000E+00 0.0E+00 ];

% Critical spectrum in infinite geometry:

B1_FLX                    (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Reaction cross sections:

B1_TOT                    (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_CAPT                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_ABS                    (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_FISS                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_NSF                    (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_NUBAR                  (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_KAPPA                  (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_INVV                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Total scattering cross sections:

B1_SCATT0                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT1                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT2                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT3                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT4                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT5                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT6                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATT7                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Total scattering production cross sections:

B1_SCATTP0                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP1                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP2                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP3                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP4                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP5                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP6                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SCATTP7                (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Diffusion parameters:

B1_TRANSPXS               (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_DIFFCOEF               (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Reduced absoption and removal:

B1_RABSXS                 (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_REMXS                  (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Poison cross sections:

B1_I135_YIELD             (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_XE135_YIELD            (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_PM149_YIELD            (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SM149_YIELD            (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_I135_MICRO_ABS         (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_XE135_MICRO_ABS        (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_PM149_MICRO_ABS        (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SM149_MICRO_ABS        (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_XE135_MACRO_ABS        (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SM149_MACRO_ABS        (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Fission spectra:

B1_CHIT                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_CHIP                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_CHID                   (idx, [1:   4]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Scattering matrixes:

B1_S0                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S1                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S2                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S3                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S4                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S5                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S6                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_S7                     (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Scattering production matrixes:

B1_SP0                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP1                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP2                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP3                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP4                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP5                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP6                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];
B1_SP7                    (idx, [1:   8]) = [  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00  0.00000E+00 0.0E+00 ];

% Delayed neutron parameters (Meulekamp method):

BETA_EFF                  (idx, [1:  14]) = [  6.75228E-03 0.00171  2.15226E-04 0.00998  1.12083E-03 0.00417  1.09111E-03 0.00427  3.07769E-03 0.00247  9.21188E-04 0.00502  3.26246E-04 0.00832 ];
LAMBDA                    (idx, [1:  14]) = [  7.71596E-01 0.00431  1.24905E-02 7.5E-07  3.17955E-02 2.9E-05  1.09474E-01 3.4E-05  3.17455E-01 3.2E-05  1.35229E+00 2.9E-05  8.67573E+00 0.00021 ];