Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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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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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.

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.

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.

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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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.

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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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).

- 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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Package ID | Computer language |
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NEA-0664/01 | FORTRAN-IV |

NEA-0664/03 | FORTRAN-77 |

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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 |

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