 ********************************************************
 *                    DCHAIN-PHITS                      *
 *                       (spd)                          *
 *                     ---------                        *
 *  transmutaion calculation code from PHITS yield data *
 *  and/or target material irradiated by neutrons       *
 ********************************************************
 *  version: 3.20  Last Modified  (2020/04/09)          *
 ********************************************************


 echo-back print of input data -------------------------------------------------------------------------------------------------
 line : input data card
    1 :     htitle = Test-calc
    2 :      imode =       2
    3 :      jmode =       2
    4 :      idivs =      50
    5 :     ichain =     100
    6 :     itdecs =       1
    7 :     itdecn =       1
    8 :     isomtr =       2
    9 :     ifisyd =       0
   10 :     ifisye =       0
   11 :    ixsrall =       1
   12 :    inxslib =     100
   13 :    idcylib =       5
   14 :      iyild =       2
   15 :      iggrp =       3
   16 :     ibetap =       1
   17 :      acmin =  1.0000E-20
   18 :     istabl =       0
   19 :     igsdef =       1
   20 :     igsorg =       1
   21 :    iwrtchn =       1
   22 :    chrlvth = -1.0000E+00
   23 :    iwrchdt =       0
   24 :    iwrchss =       0
   25 :    idosecf =       1
   26 :        amp =  1.6022E-04
   27 :      ebeam =  3.0000E+00
   28 :     prodnp =  1.0000E+00
   29 :     itstep =       4
   30 :       1.0000E+01 h  1.0000E+00
   31 :       5.0000E+00 h  0.0000E+00
   32 :       1.0000E+01 h  1.0000E+00
   33 :       1.0010E+01 y  0.0000E+00
   34 :      itout =      19
   35 :       1.0000E+00 h
   36 :       5.0000E+00 h
   37 :       1.0000E+01 h
   38 :       1.2500E+01 h
   39 :       1.5000E+01 h
   40 :       2.0000E+01 h
   41 :       2.5000E+01 h
   42 :      -1.0000E+01 s
   43 :      -1.0000E+00 m
   44 :      -1.0000E+01 m
   45 :      -1.0000E+00 h
   46 :      -1.0000E+01 h
   47 :      -1.0000E+00 d
   48 :      -1.0000E+01 d
   49 :      -1.0000E+02 d
   50 :      -1.0000E+00 y
   51 :      -2.6000E+00 y
   52 :      -5.0000E+00 y
   53 :      -1.0000E+01 y
   54 :     inmtcf =       1
   55 :   itdchout =       1
   56 :    hhnmtcf = example_Na22.dyld
   57 :   iertdcho =       1
   58 :    henmtcf = example_Na22_err.dyld
   59 :   iredufmt =       1
   60 :    irdonce =       1
   61 :     iregon =      2
   62 :    DUMMY001        2    1  6.3948E+09   example_Na22.dtrk  1.0000E+00
   63 :    F-19      1.5853E-01
   64 :    DUMMY002        4   24  2.8552E+05   example_Na22.dtrk  1.0000E+00
   65 :    C-12      1.5873E-04
   66 :    C-13      1.7816E-06
   67 :   Si-28      7.9122E-04
   68 :   Si-29      4.0063E-05
   69 :   Si-30      2.6594E-05
   70 :    P-31      3.5785E-05
   71 :    S-32      2.1419E-05
   72 :    S-33      1.6906E-07
   73 :    S-34      9.4898E-07
   74 :    S-36      4.5082E-09
   75 :   Cr-50      7.6509E-04
   76 :   Cr-52      1.4754E-02
   77 :   Cr-53      1.6730E-03
   78 :   Cr-54      4.1644E-04
   79 :   Mn-55      8.7718E-04
   80 :   Fe-54      3.5393E-03
   81 :   Fe-56      5.5559E-02
   82 :   Fe-57      1.2831E-03
   83 :   Fe-58      1.7076E-04
   84 :   Ni-58      5.1701E-03
   85 :   Ni-60      1.9915E-03
   86 :   Ni-61      8.6577E-05
   87 :   Ni-62      2.7598E-04
   88 :   Ni-64      7.0325E-05
   89 :   angelout = 1
   90 :   phitsout = 1
   91 : end
 -------------------------------------------------------------------------------------------------------------------------------

 << start of input data >>

 problem title: Test-calc                                                                                                                           

 primary control data
  (1) imode              2 : calculation mode
                             0 = activity
                             1 = activity and decay heat
                             2 = activity, decay heat and gamma-ray spectrum
  (2) jmode              2 : mode selection of particle beam and neutron irradiation
                             0 = particle beam irradiation
                             1 = irradiation with neutron flux below 20 [MeV]
                             2 = particle beam and neutron irradiation
                            -1 = decay (no irradiation)

 first calculation condition data
  (1) itstep             4 : number of time steps for irradiation and cooling (default=1)
  (2) itout             19 : number of output time of result (default=1)
  (3) idivs             50 : number of divisions of irradiation time step (default=50)
  (4) iregon             2 : number of processing regions (or cells) (default=1; it must be greater than 1)
  (5) inmtcf             1 : number of processing nmtc yield files (default=1; maximum=10) (if inmtcf>1, card 9 needs)
  (6) ichain           100 : length and number of linear chains for decay (default=100)
  (7) itdecs             1 : option of target decreasing by beam irradiation
                             0 = no decrease (default)
                             1 = decrease
  (8) itdecn             1 : option of target decreasing by neutron irradiation
                             0 = no decrease (default)
                             1 = decrease
  (9) isomtr             2 : option of isomeric state of nuclide reading from yield file
                             0 = isomeric and ground state (default)
                             1 = ground state
                             2 = equal-probability division of isomeric and ground state
  (-) ixsrall            1 : option of accelerating calculation by keeping cross section data always in system memory
                             0 = no, reread xs lib once per region (default)
                             1 = yes, read xs lib once, store it, and reuse in each
                                region (faster for multi-region but uses more memory)
 (10) ifisyd             0 : option of fission yield by neutron irradiation
                             0 = no fission
                             1 = (n,f) yield (default)
                             2 = (n,f) and spontaneous fission yields
 (11) ifisye             0 : option of use of fission yield from evaluated nuclear data file (if ifisyd>0, effective)
                             0 = no use  (default)
                             1 = thermal neutron field from endf/b-vi
                             2 = fast    neutron field from endf/b-vi
                             3 = fusion  neutron field from endf/b-vi
                            11 = thermal neutron field from jndc-fp_v2
                            12 = fast    neutron field from jndc-fp_v2
                            13 = fusion  neutron field from jndc-fp_v2
 (12) inxslib          100 : option of neutron reaction cross section data library
                                  hnxslib   (h-JP-US-EU selected here)
                            -1 = custom-lib = custom library specified by hnxslib parameter
                             0,40 =            = (default) JEFF-3.1A (DCHAIN-SP 2010)
                             1    = Legacy2001 = FENDL/A-2.0 (original library from DCHAIN-SP 2001)
                             2,20 = JENDL-AD17 = JENDL/AD-2017 (added in 2019)
                             21   = JENDL-4-0- = JENDL-4.0     (added in 2020)
                             30   = ENDF-B-7-1 = ENDF/B-VII.1  (added in 2020)
                             31   = ENDF-B-8-0 = ENDF/B-VIII.0 (added in 2020)
                             41   = JEFF-3-3-- = JEFF-3.3      (added in 2020)
                             50   = FENDL-A-30 = FENDL/A-3.0   (added in 2020)
                             51   = EAF-2010-- = EAF-2010      (added in 2020)
                             60   = BROND-3-1- = BROND-3.1     (added in 2020)
                             70   = CENDL-3-1- = CENDL-3.1     (added in 2020)
                             90   = TENDL-2017 = TENDL-2017    (added in 2020)
                             100  = h-JP-US-EU = hybrid lib of JENDL/AD-2017 + JENDL-4.0 + ENDF/B-VIII.0 + JEFF-3.3 + FENDL/A-3.0    (added in 2020)
                             101  = h-US-JP-EU = hybrid lib of ENDF/B-VIII.0 + JENDL/AD-2017 + JENDL-4.0 + JEFF-3.3 + FENDL/A-3.0    (added in 2020)
                             102  = h-EU-US-JP = hybrid lib of JEFF-3.3 + FENDL/A-3.0 + ENDF/B-VIII.0 + JENDL/AD-2017 + JENDL-4.0    (added in 2020)
                             120  = h-JENDLAD4 = hybrid lib of JENDL/AD-2017 + JENDL-4.0    (added in 2020)
 (12) idcylib            5 : option of decay data library
                                  hdcylib   (J15-EB8-ES selected here)
                            -1 = custom-lib = custom library specified by hdcylib parameter
                             0 =            = (default) revised original decay data library (DCHAIN-SP 2010)
                             1 = Legacy2001 = original decay data library (DCHAIN-SP 2001)
                             2 = JENDLDDF15 = JENDL/DDF-2015 (added in 2019)
                             3 = ENDFBVIII0 = ENDF/B-VIII.0 (added in 2019)
                             4 = EB8-J15-ES = hybrid library from ENDF/B-VIII.0, JENDL/DDF-2015, and ENSDF (added in 2019)
                             5 = J15-EB8-ES = hybrid library from JENDL/DDF-2015, ENDF/B-VIII.0, and ENSDF (added in 2019)

 output condition data
  (1) iyild              2 : option of yield file output at last output time
                             0 = no output
                             1 = output of decayed nuclide yield file (default)
                             2 = output of decayed nuclide yield file (including target nuclides)
  (2) iggrp              3 : option of gamma-ray spectrum group (if imode>1, effective)
                             0 = no effect (if imode<2)
                             1 = hilo86    --- 22 groups   (20.0 to 0.0   MeV)
                             2 = bermuda   --- 41+3 groups (20.0 to 0.0   MeV)
                             3 = vitamin-j --- 42 groups   (50.0 to 0.001 MeV)
                             4 = thida-2   --- 54 groups   ( 3.0 to 0.03  MeV)
                             5 = thida-2   --- 78 groups   ( 7.6 to 0.03  MeV)
                             6 = fns       --- 40 groups   (14.0 to 0.01  MeV)
                            99 = fispact3  --- 23+1 groups (20.0 to 0.0   MeV)
  (3) ibetap             1 : option of annihilation gamma-ray by beta(+) decay (if imode>1, effective)
                             0 = no annihilation gamma-ray
                             1 = include annihilation gamma-ray (default)
  (4) acmin     1.0000E-20 : lower limitation value for printing on activation file
                             0.0 = automatic lower limitation of activity (acmin=total*1.0e-10)(default)
                             > 0., lower limitation of acitivity [Bq/cc]
                             < 0., lower limitation of produced nuclides [n/cm**3]
  (5) istabl             0 : option for printing of stable nuclides on activation file
                             0 = no print (default)
                             1 = print
  (6) igsdef             1 : option for outputing the gamma-ray source cards for mcnp from residual activities
                             (if imode>1 and iggrp>0, effective)
                             0 = no output
                             1 = output to "out-gsdef" file (default)
  (7) iprtb1             0 : option for outputing of classification by half-life and radiation control
                             0 = no output (Fixed)
                             1 = output to "out-class" file (old default)
  (8) iprtb2             0 : option for outputing of tabulated activation and decay heat for specified nuclides
                             to "out-table-a" and "out-table-h" files
                             0 = no output (Fixed)
                             1 = output the specified number (rprtb2) of dominant nuclides selected automatically (old default)
                             2 = output nuclides above the specified ratio (rprtb2)
                             3 = output the number (rprtb2) of nuclides specified on card 8 (if negative, no sorting with za)
  (9) rprtb2       0.00000 : sub-option for outputing of tabulated activation and decay heat for specified nuclides
                             (if |iprtb2|>0, effective)
                              iprtb2 =1 : the number of nuclides selected automatically
                              iprtb2 =2 : the specified ratio to total activation and decay heat [%]
                             |iprtb2|=3 : the number of nuclides specified on card 8
 (10) iprtb3             0 : option for outputing of tabulated activation and decay heat in all regions for specified nuclides
                             (if iregon>1, effective)
                             0 = no output (Fixed)
                             n = output the number (n) of nuclides specified on card 8
                            -1 = output the nuclides as same as |iprtb2|=3
 (11) igsorg             1 : option to survey the original nuclide produced decay gamma-ray spectrum
                             0 = no effect
                             1 = survey the origianl nuclide (default)
  (-) iwrtchn            1 : option of writing output file containing decay chain information
                             0 = file is NOT written (default)
                             1 = decay chain info file is written
  (-) chrlvth     -1.00000 : decay chain relevancy threshold
                             This controls which decay chains are written to the file.
                             There are often very many irrelevant chains contributing
                             nothing or extremely little to a nuclide inventory, so 
                             this option allows for restricting this behavior.
                             This option only works when IWRTCHN=1.
                             < 0.0 : threshold for change in each nuclides inventory in atoms/cm^3 (default = -1)
                             = 0.0 : no threshold, all chains are listed regardless of relevancy (includes chains contributing nothing to inventory)
                                 Note: This can significantly increase the .DCS filesize
                             > 0.0 & <= 10.0 : threshold of fractional change in each nuclides inventory is specified
                             > 10.0 : threshold of change in each nuclides totalactivity in Bq
  (-) iwrchdt            0 : option of writing decay chain per nuclide inventory change information
                             This option toggles printing of a breakdown of where
                             the changes in a nuclides inventory are coming from,
                             looking at the links in the chain and beam vs decay/reactions.
                             This option only works when IWRTCHN=1.
                             0 = this extra information is NOT written (default)
                             1 = this extra decay chain information IS written
  (-) iwrchss            0 : option of writing decay chain substep information
                             Irradiation time steps are subdivided IDIVS times; this
                             value allows toggling of decay chain output from the many
                             time substeps during the irradiation time steps.
                             This option only works when IWRTCHN=1.
                             0 = decay chain info written for only final time steps/substeps (default)
                             1 = decay chain info written for ALL time steps/substeps
                                 Note: This can significantly increase the .DCS filesize
  (-) iwrchnuc            0: option of writing only specified nuclides to decay chain scheme file
                             This option only works when IWRTCHN=1.
                             0 = all nuclides written (default)
                             N = N nuclides listed on the next N lines are written
  (-) idosecf            1 : option of photon fluence to dose coefficients
                             Photon fluences from each nuclide are multiplied by these
                             fluence to effective dose or ambient dose equivalent
                             coefficients to obtain the final dose values reported.
                             0 = legacy coefficients (default)
                             1 = AP,     antero-posterior, effective dose, ICRP 116
                             2 = PA,     postero-anterior, effective dose, ICRP 116
                             3 = LLAT,   left lateral,     effective dose, ICRP 116
                             4 = RLAT,   right lateral,    effective dose, ICRP 116
                             5 = ROT,    rotational,       effective dose, ICRP 116
                             6 = ISO,    isotropic,        effective dose, ICRP 116
                             7 = H*(10),    ambient dose equivalent,       ICRP 74

 spallation data
  (1) amp       1.6022E-04 : proton beam current [mA]
  (2) ebeam     3.0000E+00 : proton beam energy [GeV]
  (3) prodnp    1.0000E+00 : the number of produced neutrons per a source proton (n/p ratio)

 time histories of irradiation and cooling
   no.       time      time step [s]    rel.beam
    1          10 [h]    3.60000E+04  1.0000E+00
    2          15 [h]    1.80000E+04  0.0000E+00
    3  1.0417E+00 [d]    3.60000E+04  1.0000E+00
    4  1.0013E+01 [y]    3.15892E+08  0.0000E+00

 output times of result
   no.      time [s]     input specification
    1    3.60000E+03   :       1.0000E+00 h
    2    1.80000E+04   :       5.0000E+00 h
    3    3.60000E+04   :       1.0000E+01 h
    4    4.50000E+04   :       1.2500E+01 h
    5    5.40000E+04   :       1.5000E+01 h
    6    7.20000E+04   :       2.0000E+01 h
    7    9.00000E+04   :       2.5000E+01 h
    8    9.00100E+04   :      -1.0000E+01 s
    9    9.00600E+04   :      -1.0000E+00 m
   10    9.06000E+04   :      -1.0000E+01 m
   11    9.36000E+04   :      -1.0000E+00 h
   12    1.26000E+05   :      -1.0000E+01 h
   13    1.76400E+05   :      -1.0000E+00 d
   14    9.54000E+05   :      -1.0000E+01 d
   15    8.73000E+06   :      -1.0000E+02 d
   16    3.16476E+07   :      -1.0000E+00 y
   17    8.21398E+07   :      -2.6000E+00 y
   18    1.57878E+08   :      -5.0000E+00 y
   19    3.15666E+08   :      -1.0000E+01 y

 description of regionwise calculation condition data
  (1) hregcmm(*)           : label or comment for this region (default="reg.###"; maximum 10 characters)
  (2) iregs(*)             : region number for calculating activity in yield file (default=0)
                             (if zero, yield summed in all region is used.)
                             (if -1, yield file is not used.)
  (3) itgncls(*)           : number of nuclides in a target material (default=0) (if itgncls>0, card 10a needs)
  (4) mcnptals(*)          : option of tally number in a mcnp output-list file
                             0 = no use (Fixed)
                             n = mcnp tally number given neutron spectrum
  (5) mcnpcels(*)          : option of cell number for the mcnp tally (if mcnptals>0, effective)
                             0 = no effect (Fixed)
                             n = the cell, surface or detector number in the tally
                            -n = sequential number of the cell, surface or detector in the tally
  (6) mcnpvols(*)          : option of cell volume for the mcnp tally in mcnp list file
                             0 = no effect and use volumes (Fixed)
                             n = the cell number in mcnp calculation
                            -1 = use the cell number as same as mcnpcels
  (7) mcnpmats(*)          : option of mcnp cell material in mcnp list file as target material
                             0 = no effect (Fixed)
                             n = the cell number in mcnp calculation
                            -1 = use the cell number as same as mcnpcels
  (8) fluxs(*)             : neutron total flux intensity [n/cm**2/s]  (neutron below 20 [MeV])
                             0 = no neutron flux (default)
                            -1 = if use n.flux file: intensity uses it in the file
                                 if use mcnp list file: intensity calculates from amp, prodnp (on card 4) and total flux
                             0 < neutron total flux intensity

  (-) itdchout           1 : Read file switching flag.
                             0 = used nmtc_yield & n.flux files
                             1 = used *.dyld & *.dtrak files
  (9) hnfluxs              : name of neutron spectrum file with *.dtrk format (maximum 40 characters)
 (10) volumes(*)           : volume of target region [cm**3] (default=1.0) (if mcnpvols.ne.0, ineffective)

  (-) iertdcho           1 : Read file switching flag.
                             0 = no uncertainty files to read
                             1 = use *_err.dyld file (and err column in *.dtrak)

  (-) iredufmt           1 : *.dtrk/*.dyld file syntax
                             0 = T-Track axis=eng flux (default)
                             1 = T-Track axis=dchain flux for reduced file size 
                                 and T-Yield special reduced format

  (-) irdonce           1  : *.dtrk file rereading flag
                             0 = Flux file closed/reopened in each region (default)
                             1 = Flux file only closed/reopened when filename changes

                        itg  mcnp  mcnp  mcnp  mcnp
  no.   hregcmm iregs  ncls  tals  cels  vols  mats        fluxs  hnfluxs                                       volumes
   1 DUMMY001       2     1     0     0     0     0  6.39480E+09  example_Na22.dtrk                         1.00000E+00
   2 DUMMY002       4    24     0     0     0     0  2.85520E+05  example_Na22.dtrk                         1.00000E+00

 target nuclides  (positive: atomic number density [10**24/cm**3] ;  negative: activity [Bq/cc])
   no.   1 region ...... no. of nuclides=   1
     nuclide        za   no.density     nuclide        za   no.density     nuclide        za   no.density
      F  19     9019.0  1.58530E-01
   no.   2 region ...... no. of nuclides=  24
     nuclide        za   no.density     nuclide        za   no.density     nuclide        za   no.density
      C  12     6012.0  1.58730E-04      C  13     6013.0  1.78160E-06      Si 28    14028.0  7.91220E-04
      Si 29    14029.0  4.00630E-05      Si 30    14030.0  2.65940E-05      P  31    15031.0  3.57850E-05
      S  32    16032.0  2.14190E-05      S  33    16033.0  1.69060E-07      S  34    16034.0  9.48980E-07
      S  36    16036.0  4.50820E-09      Cr 50    24050.0  7.65090E-04      Cr 52    24052.0  1.47540E-02
      Cr 53    24053.0  1.67300E-03      Cr 54    24054.0  4.16440E-04      Mn 55    25055.0  8.77180E-04
      Fe 54    26054.0  3.53930E-03      Fe 56    26056.0  5.55590E-02      Fe 57    26057.0  1.28310E-03
      Fe 58    26058.0  1.70760E-04      Ni 58    28058.0  5.17010E-03      Ni 60    28060.0  1.99150E-03
      Ni 61    28061.0  8.65770E-05      Ni 62    28062.0  2.75980E-04      Ni 64    28064.0  7.03250E-05

 output data condition for PHITS
 (1) phitsdm             0 : Specification method
                             0 = off (default)
                             1 = Specify by number of nuclides
                             2 = Specify by Energy level

 2D plot output data condition for ANGEL
 (1) iplotmode           0 : 2D plot mode
                             0 = off (default)
                             1,..3,..5,..7 = xy plot on
                             ..2,3,....6,7 = xz plot on
                             ......4,5,6,7 = yz plot on

 regionwise output data condition for ANGEL
 (1) angelout            1 : output mode
                             0 = off (default)
                             1 = on
 (2) angelout_act        1 : activity [Bq]
                             0 = off (default)
                             1 = on
 (3) angelout_heat       1 : decay heat [W]
                             0 = off (default)
                             1 = on
 (4) angelout_heat_beta  1 : decay heat(beta) [W]
                             0 = off (default)
                             1 = on
 (5) angelout_heat_gamma 1 : decay heat(gamma) [W]
                             0 = off (default)
                             1 = on
 (6) angelout_heat_alpha 1 : decay heat(alpha) [W]
                             0 = off (default)
                             1 = on
 (7) angelout_dose       1 : dose-rate [uSv/h*m^2]
                             0 = off (default)
                             1 = on
 (8)                     2 : number of output regions
                         1 : sum total of all regions
                             0 = off
                             1 = on (default)
 output region name(s) 
DUMMY001    DUMMY002  

 gamma-ray source card output for PHITS
 (1) phitsout            1 : output mode
                             0 = off (default)
                             1 = on (all data printed to single file)
                             2 = on (separate files for each output time step)

 << end of input data >>


 information of variable dimension size
   supplied size .....  3500000
   used size .........  3328251

 the number of nuclides in the decay data library =    4012

 the number of nuclides in the dose-rate data =    4012
 
 Reading in neutron reaction cross section library...
 the number of reactions found =       19965



 <>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>
 <>-<>   no.     1  regionwise calculation data     <>-<>
 <>-<>   region label : DUMMY001                    <>-<>
 <>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>

  region volume ............  1.00000E+00 [cm**3]        nmtc region number .......            2
  mcnp tally data ..........            0 (mcnptal)                                            0 (mcnpcel)
                                        0 (mcnpvol)                                            0 (mcnpmat)
  no. of target materials ..            1
  neutron flux .............  6.39480E+09 [n/cm**2/s]    flux file name ........... example_Na22.dtrk                       
  target decreasing by p ...            1                target decreasing by n ...            1 (0/1=no/yes)
  target nuclides  (positive: atomic number density [10**24/cm**3] ;  negative: activity [Bq/cc])
     nuclide        za   no.density     nuclide        za   no.density     nuclide        za   no.density
      F  19     9019.0  1.58530E-01

 the number of kinds of produced nuclides by nmtc calculation =           20
 total yield of produced nuclides per a source                =  6.05373E-01
 nuclide     yield  nuclide     yield  nuclide     yield  nuclide     yield  nuclide     yield  nuclide     yield
 -----------------  -----------------  -----------------  -----------------  -----------------  -----------------
  H   2  9.100E-05   Li  7  2.000E-06   O  16  1.000E-05   F  19 -3.953E-01   Ne 21  8.730E-04                   
  H   3  2.300E-05   B  11  3.000E-06   O  17  4.000E-06   F  20  1.000E-06   Ne 22  3.160E-04                   
  He  3  1.000E-06   C  12  3.000E-06   O  18  2.600E-05   F  21  7.000E-06   Na 21  2.300E-05                   
  He  4  9.983E-01   N  15  1.750E-04   F  18  1.580E-04   Ne 20  1.790E-04   Na 22  4.780E-04                   
Warning: Negative yield data was found.
    F  19 : -3.953E-01
  Please check about whether this entry is correct or not./
 
 Reading neutron energy spectrum:         1968  groups

 correction of target decreasing
 macroscopic nonelastic cross section of target material =  5.5456E-02 [1/cm]
 total nuclide numbers of target material                =  1.5853E+23


 start of irradiation and cooling calculation   ... cpu time      0.00 [s]
 --------------------------------------------
    initial proton  flux =  1.00001E+12 [n/cm**2/s]
    initial neutron flux =  6.39480E+09 [n/cm**2/s]  below 20 MeV
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  1.19586E+08 [Bq/cc] ( 1.19586E+08 [Bq])  at         60 [m]
  summation of decay heat   =  6.23830E-05 [W/cc]  ( 6.23830E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  2.04685E+08 [Bq/cc] ( 2.04685E+08 [Bq])  at          5 [h]
  summation of decay heat   =  7.91667E-05 [W/cc]  ( 7.91667E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  2.25100E+08 [Bq/cc] ( 2.25100E+08 [Bq])  at         10 [h]
  summation of decay heat   =  8.32038E-05 [W/cc]  ( 8.32038E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  6.04859E+07 [Bq/cc] ( 6.04859E+07 [Bq])  at 1.2500E+01 [h]
  summation of decay heat   =  1.19485E-05 [W/cc]  ( 1.19485E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  2.35475E+07 [Bq/cc] ( 2.35475E+07 [Bq])  at         15 [h]
  summation of decay heat   =  4.66796E-06 [W/cc]  ( 4.66796E-06 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  2.08352E+08 [Bq/cc] ( 2.08352E+08 [Bq])  at         20 [h]
  summation of decay heat   =  7.99161E-05 [W/cc]  ( 7.99161E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  2.25776E+08 [Bq/cc] ( 2.25776E+08 [Bq])  at 1.0417E+00 [d]
  summation of decay heat   =  8.33638E-05 [W/cc]  ( 8.33638E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.91610E+08 [Bq/cc] ( 1.91610E+08 [Bq])  at 1.0418E+00 [d]
  summation of decay heat   =  5.39226E-05 [W/cc]  ( 5.39226E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.60286E+08 [Bq/cc] ( 1.60286E+08 [Bq])  at 1.0424E+00 [d]
  summation of decay heat   =  3.25478E-05 [W/cc]  ( 3.25478E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.46854E+08 [Bq/cc] ( 1.46854E+08 [Bq])  at 1.0486E+00 [d]
  summation of decay heat   =  2.89984E-05 [W/cc]  ( 2.89984E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.07173E+08 [Bq/cc] ( 1.07173E+08 [Bq])  at 1.0833E+00 [d]
  summation of decay heat   =  2.11773E-05 [W/cc]  ( 2.11773E-05 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  3.82491E+06 [Bq/cc] ( 3.82491E+06 [Bq])  at 1.4583E+00 [d]
  summation of decay heat   =  8.07353E-07 [W/cc]  ( 8.07353E-07 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  3.10749E+05 [Bq/cc] ( 3.10749E+05 [Bq])  at 2.0417E+00 [d]
  summation of decay heat   =  1.14690E-07 [W/cc]  ( 1.14690E-07 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  2.91296E+05 [Bq/cc] ( 2.91296E+05 [Bq])  at 1.1042E+01 [d]
  summation of decay heat   =  1.10503E-07 [W/cc]  ( 1.10503E-07 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  2.72945E+05 [Bq/cc] ( 2.72945E+05 [Bq])  at 1.0104E+02 [d]
  summation of decay heat   =  1.03484E-07 [W/cc]  ( 1.03484E-07 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  2.25353E+05 [Bq/cc] ( 2.25353E+05 [Bq])  at 1.0029E+00 [y]
  summation of decay heat   =  8.52855E-08 [W/cc]  ( 8.52855E-08 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.47916E+05 [Bq/cc] ( 1.47916E+05 [Bq])  at 2.6029E+00 [y]
  summation of decay heat   =  5.56945E-08 [W/cc]  ( 5.56945E-08 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  7.89712E+04 [Bq/cc] ( 7.89712E+04 [Bq])  at 5.0029E+00 [y]
  summation of decay heat   =  2.93915E-08 [W/cc]  ( 2.93915E-08 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  2.19839E+04 [Bq/cc] ( 2.19839E+04 [Bq])  at 1.0003E+01 [y]
  summation of decay heat   =  7.76143E-09 [W/cc]  ( 7.76143E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  summation of decay yields =  1.58530E+23 [n]

 /_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/
 _/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/   end of irradiation and decay calculation for this region  /_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_
 /_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/



 <>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>
 <>-<>   no.     2  regionwise calculation data     <>-<>
 <>-<>   region label : DUMMY002                    <>-<>
 <>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>-<>

  region volume ............  1.00000E+00 [cm**3]        nmtc region number .......            4
  mcnp tally data ..........            0 (mcnptal)                                            0 (mcnpcel)
                                        0 (mcnpvol)                                            0 (mcnpmat)
  no. of target materials ..           24
  neutron flux .............  2.85520E+05 [n/cm**2/s]    flux file name ........... example_Na22.dtrk                       
  target decreasing by p ...            1                target decreasing by n ...            1 (0/1=no/yes)
  target nuclides  (positive: atomic number density [10**24/cm**3] ;  negative: activity [Bq/cc])
     nuclide        za   no.density     nuclide        za   no.density     nuclide        za   no.density
      C  12     6012.0  1.58730E-04      C  13     6013.0  1.78160E-06      Si 28    14028.0  7.91220E-04
      Si 29    14029.0  4.00630E-05      Si 30    14030.0  2.65940E-05      P  31    15031.0  3.57850E-05
      S  32    16032.0  2.14190E-05      S  33    16033.0  1.69060E-07      S  34    16034.0  9.48980E-07
      S  36    16036.0  4.50820E-09      Cr 50    24050.0  7.65090E-04      Cr 52    24052.0  1.47540E-02
      Cr 53    24053.0  1.67300E-03      Cr 54    24054.0  4.16440E-04      Mn 55    25055.0  8.77180E-04
      Fe 54    26054.0  3.53930E-03      Fe 56    26056.0  5.55590E-02      Fe 57    26057.0  1.28310E-03
      Fe 58    26058.0  1.70760E-04      Ni 58    28058.0  5.17010E-03      Ni 60    28060.0  1.99150E-03
      Ni 61    28061.0  8.65770E-05      Ni 62    28062.0  2.75980E-04      Ni 64    28064.0  7.03250E-05

 the number of kinds of produced nuclides by nmtc calculation =            7
 total yield of produced nuclides per a source                =  0.00000E+00
 nuclide     yield  nuclide     yield  nuclide     yield  nuclide     yield  nuclide     yield  nuclide     yield
 -----------------  -----------------  -----------------  -----------------  -----------------  -----------------
  He  4  1.000E-06   Cr 52 -1.000E-06   Fe 56 -2.000E-06   Co 58m 1.000E-06                                      
  F  19 -1.000E-06   Fe 54  1.000E-06   Co 58  1.000E-06                                                         
Warning: Negative yield data was found.
    F  19 : -1.000E-06
  Please check about whether this entry is correct or not./
Warning: Negative yield data was found.
    Cr 52 : -1.000E-06
  Please check about whether this entry is correct or not./
Warning: Negative yield data was found.
    Fe 56 : -2.000E-06
  Please check about whether this entry is correct or not./
 
 Reading neutron energy spectrum:         1968  groups

 correction of target decreasing
 macroscopic nonelastic cross section of target material =  6.6082E-02 [1/cm]
 total nuclide numbers of target material                =  8.7709E+22


 start of irradiation and cooling calculation   ... cpu time      0.00 [s]
 --------------------------------------------
    initial proton  flux =  1.00001E+12 [n/cm**2/s]
    initial neutron flux =  2.85520E+05 [n/cm**2/s]  below 20 MeV
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  7.37244E+04 [Bq/cc] ( 7.37244E+04 [Bq])  at         60 [m]
  summation of decay heat   =  3.76681E-10 [W/cc]  ( 3.76681E-10 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  3.18876E+05 [Bq/cc] ( 3.18876E+05 [Bq])  at          5 [h]
  summation of decay heat   =  1.67357E-09 [W/cc]  ( 1.67357E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  5.38099E+05 [Bq/cc] ( 5.38099E+05 [Bq])  at         10 [h]
  summation of decay heat   =  3.00709E-09 [W/cc]  ( 3.00709E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  4.46258E+05 [Bq/cc] ( 4.46258E+05 [Bq])  at 1.2500E+01 [h]
  summation of decay heat   =  2.69452E-09 [W/cc]  ( 2.69452E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  3.70356E+05 [Bq/cc] ( 3.70356E+05 [Bq])  at         15 [h]
  summation of decay heat   =  2.44920E-09 [W/cc]  ( 2.44920E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  5.74602E+05 [Bq/cc] ( 5.74602E+05 [Bq])  at         20 [h]
  summation of decay heat   =  3.75777E-09 [W/cc]  ( 3.75777E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  ratio of residual target nuclide to initial =  1.00000E+00
 
  during irradiation time ---
  summation of activity     =  7.15464E+05 [Bq/cc] ( 7.15464E+05 [Bq])  at 1.0417E+00 [d]
  summation of decay heat   =  4.84366E-09 [W/cc]  ( 4.84366E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  7.15315E+05 [Bq/cc] ( 7.15315E+05 [Bq])  at 1.0418E+00 [d]
  summation of decay heat   =  4.84279E-09 [W/cc]  ( 4.84279E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  7.14573E+05 [Bq/cc] ( 7.14573E+05 [Bq])  at 1.0424E+00 [d]
  summation of decay heat   =  4.83871E-09 [W/cc]  ( 4.83871E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  7.06630E+05 [Bq/cc] ( 7.06630E+05 [Bq])  at 1.0486E+00 [d]
  summation of decay heat   =  4.80597E-09 [W/cc]  ( 4.80597E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  6.64202E+05 [Bq/cc] ( 6.64202E+05 [Bq])  at 1.0833E+00 [d]
  summation of decay heat   =  4.66566E-09 [W/cc]  ( 4.66566E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  3.42895E+05 [Bq/cc] ( 3.42895E+05 [Bq])  at 1.4583E+00 [d]
  summation of decay heat   =  3.63492E-09 [W/cc]  ( 3.63492E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.28719E+05 [Bq/cc] ( 1.28719E+05 [Bq])  at 2.0417E+00 [d]
  summation of decay heat   =  2.95298E-09 [W/cc]  ( 2.95298E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.47522E+04 [Bq/cc] ( 1.47522E+04 [Bq])  at 1.1042E+01 [d]
  summation of decay heat   =  2.38384E-09 [W/cc]  ( 2.38384E-09 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  6.11648E+03 [Bq/cc] ( 6.11648E+03 [Bq])  at 1.0104E+02 [d]
  summation of decay heat   =  9.88377E-10 [W/cc]  ( 9.88377E-10 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  4.56822E+02 [Bq/cc] ( 4.56822E+02 [Bq])  at 1.0029E+00 [y]
  summation of decay heat   =  7.38109E-11 [W/cc]  ( 7.38109E-11 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.56477E+00 [Bq/cc] ( 1.56477E+00 [Bq])  at 2.6029E+00 [y]
  summation of decay heat   =  2.48365E-13 [W/cc]  ( 2.48365E-13 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  1.87679E-02 [Bq/cc] ( 1.87679E-02 [Bq])  at 5.0029E+00 [y]
  summation of decay heat   =  1.13572E-15 [W/cc]  ( 1.13572E-15 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
 
  during cooling time ---
  summation of activity     =  3.97782E-03 [Bq/cc] ( 3.97782E-03 [Bq])  at 1.0003E+01 [y]
  summation of decay heat   =  2.00004E-16 [W/cc]  ( 2.00004E-16 [W])
                                                                  cpu time       0.00 [s]  (      0.00 [s])
  summation of decay yields =  8.77091E+22 [n]

 /_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/
 _/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/   end of irradiation and decay calculation for this region  /_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_
 /_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/_/

 end of spd calculation process
 ------------------------------  good bye... .. .
