Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, CPU, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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Program name | Package id | Status | Status date |
---|---|---|---|

TIMOC-72 | NEA-0387/01 | Tested | 01-JUL-1975 |

TIMOC-72 | NEA-0387/02 | Tested | 01-DEC-1972 |

Machines used:

Package ID | Orig. computer | Test computer |
---|---|---|

NEA-0387/01 | UNIVAC 1106 | UNIVAC 1106 |

NEA-0387/02 | IBM 370 series | IBM 370 series |

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3. NATURE OF PHYSICAL PROBLEM SOLVED

TIMOC solves the energy and time dependent (or stationary) homogeneous or inhomogeneous neutron transport equation in three-dimensional geometries. The program can treat all commonly used scattering kernels, such as absorption, fission, isotropic and anisotropic elastic scattering, level excitation, the evaporation model, and the energy transfer matrix model, which includes (n,2n) reactions. The exchangeable geometry routines consist at present of (a) periodical multilayer slab, spherical and cylindrical lattices, (b) an elaborate three-dimensional cylindrical geometry which allows all kinds of subdivisions, (c) the very flexible O5R geometry routine which is able to describe any body combinations with surfaces of second order. The program samples the stationary or time-energy-region dependent fluxes as well as the transmission ratios between geometrical regions and the following integral quantities or eigenvalues, the leakage rate, the slowing down density, the production to source ratio, the multiplication factor based on flux and collision estimator, the mean production time, the mean destruction time, time distribution of production and destruction, the fission rates, the energy dependent absorption rates, the energy deposition due to elastic scattering for the different geometrical regions.

TIMOC solves the energy and time dependent (or stationary) homogeneous or inhomogeneous neutron transport equation in three-dimensional geometries. The program can treat all commonly used scattering kernels, such as absorption, fission, isotropic and anisotropic elastic scattering, level excitation, the evaporation model, and the energy transfer matrix model, which includes (n,2n) reactions. The exchangeable geometry routines consist at present of (a) periodical multilayer slab, spherical and cylindrical lattices, (b) an elaborate three-dimensional cylindrical geometry which allows all kinds of subdivisions, (c) the very flexible O5R geometry routine which is able to describe any body combinations with surfaces of second order. The program samples the stationary or time-energy-region dependent fluxes as well as the transmission ratios between geometrical regions and the following integral quantities or eigenvalues, the leakage rate, the slowing down density, the production to source ratio, the multiplication factor based on flux and collision estimator, the mean production time, the mean destruction time, time distribution of production and destruction, the fission rates, the energy dependent absorption rates, the energy deposition due to elastic scattering for the different geometrical regions.

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4. METHOD OF SOLUTION

TIMOC is a Monte Carlo program and uses several, partially optional variance reducing techniques, such as the method of expected values (weight factor), Russian roulette, the method of fractional generated neutrons, double sampling, semi-systematic sampling and the method of expected leakage probability. Within the neutron lifetime a discrete energy value is given after each collision process. The nuclear data input is however done by group averaged cross sections. The program can generate the neutron fluxes either resulting from an external source or in the form of fundamental mode distributions by a special source iteration procedure. In this latter case, the sampling of eigenvalues is based on the life cycle.

TIMOC is a Monte Carlo program and uses several, partially optional variance reducing techniques, such as the method of expected values (weight factor), Russian roulette, the method of fractional generated neutrons, double sampling, semi-systematic sampling and the method of expected leakage probability. Within the neutron lifetime a discrete energy value is given after each collision process. The nuclear data input is however done by group averaged cross sections. The program can generate the neutron fluxes either resulting from an external source or in the form of fundamental mode distributions by a special source iteration procedure. In this latter case, the sampling of eigenvalues is based on the life cycle.

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7. UNUSUAL FEATURES OF THE PROGRAM

A special option allows the calculation of geometrical perturbation effects. In such calculations, the differential effect does not depend on the total variance of the considered quantity. The sampling of these differential effects is based on the method of similar flight paths.

A special option allows the calculation of geometrical perturbation effects. In such calculations, the differential effect does not depend on the total variance of the considered quantity. The sampling of these differential effects is based on the method of similar flight paths.

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Package ID | Status date | Status |
---|---|---|

NEA-0387/01 | 01-JUL-1975 | Tested at NEADB |

NEA-0387/02 | 01-DEC-1972 | Tested at NEADB |

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NEA-0387/01, included references:

- R. Jaarsma and H. Rief:TIMOC 72 Code Manual

EUR 5016 e (1973)

- Modification of TIMOC 72

- H. Kschwendt and H. Rief:

TIMOC - A General Purpose Monte Carlo Code for Stationary and Time

Neutron Transport

EUR 4519 e (1970)

- R.J. Jaarsma and H. Kschwendt:

Geometry Routines for Use in the TIMOC Code

- Note from INGENIEROS on TIMOC-72/J2

UNIVAC Implementation (30 May 1978)

- F.Beonio-Brocchieri and C.Daolio

CODAC 2 : A New Version of the CODAC Code Which Accepts

ENDF/B Version II Data for the Production of a Few Group Library

for TIMOC.

EUR/C-IS/816 72.e (March 1972)

- H.Krainer

CODAC, A FORTRAN IV Program to Process a TIMOC Library

From the ENDF/B File.

EUR-4512.e (1970)

NEA-0387/02, included references:

- R. Jaarsma and H. Rief:TIMOC 72 Code Manual

EUR 5016 e (1973)

- Modification of TIMOC 72

- H. Kschwendt and H. Rief:

TIMOC - A General Purpose Monte Carlo Code for Stationary and Time

Neutron Transport

EUR 4519 e (1970)

- R.J. Jaarsma and H. Kschwendt:

Geometry Routines for Use in the TIMOC Code

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Package ID | Computer language |
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NEA-0387/01 | FORTRAN-IV |

NEA-0387/02 | FORTRAN+ASSEMBLER |

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NEA-0387/01

File name | File description | Records |
---|---|---|

NEA0387_01.001 | SOURCE PROGRAM (F4) | 4586 |

NEA0387_01.002 | ASSEMBLER ROUTINE | 49 |

NEA0387_01.003 | SAMPLE PROBLEM DATA | 203 |

NEA0387_01.004 | SAMPLE PROBLEM PRINTED OUTPUT | 315 |

NEA-0387/02

File name | File description | Records |
---|---|---|

NEA0387_02.001 | INFORMATION | 3 |

NEA0387_02.002 | FORTRAN SOURCE PROGRAMMES (MAIN -PACKAGE) | 33 |

NEA0387_02.003 | FORTRAN SOURCE PROGRAMMES (NDP -PACKAGE) | 885 |

NEA0387_02.004 | FORTRAN SOURCE PROGRAMMES (RWS -PACKAGE) | 2130 |

NEA0387_02.005 | FORTRAN SOURCE PROGRAMMES (GEOM -PACKAGE) | 1417 |

NEA0387_02.006 | ASSEMBLER PROGRAMMES (LOC -PACKAGE) | 8 |

NEA0387_02.007 | ASSEMBLER PROGRAMMES (RANDOM-PACKAGE) | 549 |

NEA0387_02.008 | INPUT DATA FOR SAMPLE PROBLEM NO.1 | 203 |

NEA0387_02.009 | PRINTED OUTPUT OF SAMPLE PROBLEM NO.1 | 339 |

NEA0387_02.010 | INPUT DATA FOR SAMPLE PROBLEM NO.2 | 184 |

NEA0387_02.011 | PRINTED OUTPUT OF SAMPLE PROBLEM NO.2 | 720 |

NEA0387_02.012 | FORTRAN SOURCE PROGRAMME OF PLOTGEOM | 1054 |

NEA0387_02.013 | SAMPLE PROBLEM FOR PLOTGEOM | 79 |

NEA0387_02.014 | SAMPLE OUTPUT OF PLOTGEOM | 193 |

NEA0387_02.015 | SPECIAL VERSIONS OF SUB. STRDIR AND NDFIS | 375 |

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- F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics

Keywords: Monte Carlo method, absorption, cylinders, elastic scattering, fission, kinetics, neutron transport theory, slabs, spheres, three-dimensional.