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NEA-0664 DCHAIN-2.

DCHAIN, Isotope Buildup and Isotope Decay by 1 Point Approximation

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1. NAME OR DESIGNATION OF PROGRAM:  DCHAIN. A computer code for calculation of transmutation of nuclides.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
DCHAIN NEA-0664/01 Tested 11-JUN-1982
DCHAIN-2 NEA-0664/03 Tested 17-JUN-1991

Machines used:

Package ID Orig. computer Test computer
NEA-0664/01 IBM 3033 IBM 3033
NEA-0664/03 IBM PC IBM PC
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3. DESCRIPTION OF PROBLEM OR FUNCTION

DCHAIN analyzes radioactive growth and decay of nuclides by one-point approximation.
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4. METHOD OF SOLUTION

The code constructs the decay scheme of each nuclide in the code and breaks it up into linear chains. Accumulation of the nuclide by each linear chain is calculated analytically by the Bateman method and the total accumulation is obtained as the summation of solutions for linear chains.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The core memory size MXX for the variable dimensions is limited to 100 K and the total necessary core memory size is 128 K for the accumulation calculation by the present version of the code.

DEDIT routine
     MXX = NNUM* (NFIS = 4* NPAR + 9)
           + ISC* (NGS + 1) + 10* (NCARD + 1),

where, MXX = necessary core memory size for variable dimension              variables,
      NNUM = number of nuclides in the nuclear data library,
NCARD = number of cards to revise the nuclear data library,  NGS = number of groups for neutron reaction cross sections              (27),
NFIS = number of kinds of fission yields (10),  NPAR = the maximum number of the direct mother nuclides              allowed for each nuclide (6),
ISC = number of nuclides having neutron reaction cross              sections (100).

FPDH routine
       MXX = NMAX* (17 + 4*NPAR + NFIS)
             + LCH* (6 + 2*NCHA) + ISC* (1 + NGS + NIRR)
             + NIRR* (10 + NFIS) + NGS + NOUT* 5,

where,NMAX = number of nuclides considered in the calculation,  NPAR = the maximum number of the direct mother nuclides              allowed for each nuclide,
      NFIS = number of kinds of fission yields,
      LCHA = the limitation for the length of a linear chain,
NCHA = the maximum allowable number of linear chains allowed              for the calculation of accumulation of each nuclide,
NIRR = number of time steps for expressing the irradiation and              cooling history,
NOUT = the maximum number of time points for the output of              results.
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6. TYPICAL RUNNING TIME

Running time was 180 s for calculating accumulations of 1170 fission products for 1 irradiation-history time step and 32 output times by using a FACOM 230-75 computer which requires about double CPU time compared with a CDC 6600.

Running time is approximately proportional to number of nuclides, irradiation time steps and output times. It depends also upon complication of the decay scheme. The running time was tripled by considering neutron capture transformations in fission products.
NEA-DB executed the test case on IBM 3033 in 3 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

FPGAM code can calculate a gamma- ray spectrum of nuclides of which accumulations were calculated by DCHAIN. FPGAM can take the response function of a gamma-ray detector into consideration.

DCHAIN supersedes the FP-S code and enables linearization of any type of decay schemes.
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9. STATUS
Package ID Status date Status
NEA-0664/01 11-JUN-1982 Tested at NEADB
NEA-0664/03 17-JUN-1991 Tested at NEADB
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10. REFERENCES

- K. Tasaka:
  "DCHAIN - Code for Analysis of Build-up and Decay of Nuclides"
  JAERI 1250 (1977).
- K. Tasaka:
  "Nuclear Data Library of Fission Products for Decay Power
  Calculation"
  NUREG/CR-0705, TREE-1325 (1979).
- K. Tasaka:
  "Computer Program FPGAM for Calculating Gamma-Ray Spectrum of
  Fission Products
  JAERI-M 6898 (1977).
NEA-0664/01, included references:
- K. Tasaka:
  DCHAIN2 - A Computer Code for Calculation of Transmutation of
  Nuclides
  JAERI-M 8727 (1980).
- H. Ihara et al.:
  PROFP-Y - A Computer Code for Producing Nuclear Data Library of
  Fission Products
  JAERI-M 9714 (1981)
NEA-0664/03, included references:
- K. Tasaka:
  DCHAIN2 - A Computer Code for Calculation of Transmutation of
  Nuclides
  JAERI-M 8727 (1980).
- H. Ihara et al.:
  PROFP-Y - A Computer Code for Producing Nuclear Data Library of
  Fission Products
  JAERI-M 9714 (1981)
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11. MACHINE REQUIREMENTS:  300 kbytes of main storage on IBM 3033.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0664/01 FORTRAN-IV
NEA-0664/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
OS370/033 VS2 03.8G (IBM 3033).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

          Japan Atomic Energy Research Institute
          Tokai-mura
          Naka-gun
          Ibaraki-ken
          Japan
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16. MATERIAL AVAILABLE
NEA-0664/01
File name File description Records
NEA0664_01.001 DCHAIN INFORMATION FILE 56
NEA0664_01.002 DCHAIN, SOURCE CARD IMAGES (FORTRAN-4) 1806
NEA0664_01.003 SETB99, SOURCE CARD IMAGES (ASSEMBLER) 82
NEA0664_01.004 LIBRARY CONVERSION PROGRAM, SOURCE 74
NEA0664_01.005 LIBRARY DATA (BCD) 3688
NEA0664_01.006 DCHAIN, INPUT DATA FOR SAMPLE CASE 32
NEA0664_01.007 DCHAIN, OUTPUT OF SAMPLE CASE 2966
NEA0664_01.008 DCHAIN, JCL TO RUN SAMPLE CASE 101
NEA-0664/03
File name File description Records
NEA0664_03.001 Information file 92
NEA0664_03.002 Batch file to compile and link 15
NEA0664_03.003 Binary data library 0
NEA0664_03.004 Sample 1 input data 12
NEA0664_03.005 Sample 2 input data 19
NEA0664_03.006 Sample 3 input data 14
NEA0664_03.007 Sample 4 input data 14
NEA0664_03.008 DCHAINLI.FOR Source file 78
NEA0664_03.009 DCHMAIN Source file 198
NEA0664_03.010 DCHT source file 215
NEA0664_03.011 DEDIT Source file 345
NEA0664_03.012 FN Source file 124
NEA0664_03.013 FPDH Source file 430
NEA0664_03.014 FYCI Source file 45
NEA0664_03.015 INPUT Source file 74
NEA0664_03.016 ONPWR Source file 164
NEA0664_03.017 OUTPUT Source file 69
NEA0664_03.018 Input file to create DCHLIB.BIN 3688
NEA0664_03.019 Output on logical unit 12 30
NEA0664_03.020 Sample 1 output data 1480
NEA0664_03.021 Sample 2 output data 169
NEA0664_03.022 Sample 3 output data 62
NEA0664_03.023 Sample 4 output data 107
NEA0664_03.024 DOS file-names 23
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: daughter products, decay, isotope production, transmutation.