Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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To submit a request, click below on the link of the version you wish to order. Rules for end-users are
available here.

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

ZZ-DLC-17 | DLC-0017/01 | Tested | 01-APR-1973 |

Machines used:

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

DLC-0017/01 | Many Computers | Many Computers |

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3. NATURE OF PHYSICAL PROBLEM SOLVED

FORMAT: ANISN, DOT, or MORSE

NUMBER OF GROUPS: Coupled 86 neutron and 33 gamma-ray energy group cross sections

NUCLIDES: air (N, and O,)

ORIGIN: DNA Working Cross Section Library

WEIGHTING SPECTRUM: Cross section values for the neutron thermal group (86) were determined by assuming a Maxwellian weighting function with a constant scattering cross section and a 1/v absorption cross section.

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DLC-17 is suitable for multigroup neutron, gamma-ray, or coupled neutron and gamma-ray transport calculations in nitrogen, oxygen, or air. The retrieval program manipulates the data so that it can be used in codes such as ANISN, DOT, or MORSE.

The coupled 86 neutron and 33 gamma-ray energy group cross sections were produced by members of the ORNL mathematics division. The neutron multigroup data were produced with SUPERTOG, the neutron to gamma-ray group transfer matrices with a modified version of NUSECT, and the gamma-ray multigroup data with MUG. NUSECT is the cross section generator for O6R , but modifications had to be made to the version in the distributed code package to generate the desired gamma-ray production matrices.

FORMAT: ANISN, DOT, or MORSE

NUMBER OF GROUPS: Coupled 86 neutron and 33 gamma-ray energy group cross sections

NUCLIDES: air (N, and O,)

ORIGIN: DNA Working Cross Section Library

WEIGHTING SPECTRUM: Cross section values for the neutron thermal group (86) were determined by assuming a Maxwellian weighting function with a constant scattering cross section and a 1/v absorption cross section.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

DLC-17 is suitable for multigroup neutron, gamma-ray, or coupled neutron and gamma-ray transport calculations in nitrogen, oxygen, or air. The retrieval program manipulates the data so that it can be used in codes such as ANISN, DOT, or MORSE.

The coupled 86 neutron and 33 gamma-ray energy group cross sections were produced by members of the ORNL mathematics division. The neutron multigroup data were produced with SUPERTOG, the neutron to gamma-ray group transfer matrices with a modified version of NUSECT, and the gamma-ray multigroup data with MUG. NUSECT is the cross section generator for O6R , but modifications had to be made to the version in the distributed code package to generate the desired gamma-ray production matrices.

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4. METHOD OF SOLUTION

This data represents a P5 Legendre expansion approximation for neutron elastic scattering and gamma-ray Compton scattering.

Inelastic neutron scatter and gamma-ray production are treated as isotropic.

Cross section values for the neutron thermal group (86) were determined by assuming a Maxwellian weighting function with a constant scattering cross section and a 1/v absorption cross section.

The 86 neutron groups cover the energy range from 15 Mev to thermal and the group structure was chosen to represent the variation in the nitrogen total cross section. The 33 gamma-ray groups span the energy range from 10 to 0.01 MeV. The gamma-ray group structure was chosen with one group of width 0.2 MeV containing each nitrogen resolved line and one group of varying energy width between adjacent resolved lines.

The neutron interaction secondary gamma-ray production, and gamma-ray interaction multigroup data were generated from recent evaluations by Young and Foster. The evaluations are part of the DNA working cross section library, and the identification designations are DNA MAT 4133, MOD 1 for nitrogen and DNA MAT 4134, MOD 0 for oxygen.

This data represents a P5 Legendre expansion approximation for neutron elastic scattering and gamma-ray Compton scattering.

Inelastic neutron scatter and gamma-ray production are treated as isotropic.

Cross section values for the neutron thermal group (86) were determined by assuming a Maxwellian weighting function with a constant scattering cross section and a 1/v absorption cross section.

The 86 neutron groups cover the energy range from 15 Mev to thermal and the group structure was chosen to represent the variation in the nitrogen total cross section. The 33 gamma-ray groups span the energy range from 10 to 0.01 MeV. The gamma-ray group structure was chosen with one group of width 0.2 MeV containing each nitrogen resolved line and one group of varying energy width between adjacent resolved lines.

The neutron interaction secondary gamma-ray production, and gamma-ray interaction multigroup data were generated from recent evaluations by Young and Foster. The evaluations are part of the DNA working cross section library, and the identification designations are DNA MAT 4133, MOD 1 for nitrogen and DNA MAT 4134, MOD 0 for oxygen.

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10. REFERENCES

- E.A. Straker and B. J. McGregor:

'A Calculation of Gamma-Ray Production and Transport in Liquid

Nitrogen'

ORNL-TM-3635 (December 1971).

- L.R. Williams:

'Input Description for LIBGEN'

Informal Notes (1972).

- G.M. Reynolds and S.M. Sperling:

'A Re-Analysis of Secondary Gamma-Ray Spectra Produced in Liquid

Nitrogen by 14 MeV Neutrons'

DNA 2831F or SAI-71-550-LJ (March 1972).

- E.A. Straker and B. J. McGregor:

'A Calculation of Gamma-Ray Production and Transport in Liquid

Nitrogen'

ORNL-TM-3635 (December 1971).

- L.R. Williams:

'Input Description for LIBGEN'

Informal Notes (1972).

- G.M. Reynolds and S.M. Sperling:

'A Re-Analysis of Secondary Gamma-Ray Spectra Produced in Liquid

Nitrogen by 14 MeV Neutrons'

DNA 2831F or SAI-71-550-LJ (March 1972).

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DLC-0017/01

File name | File description | Records |
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DLC0017_01.001 | 119-GRP COUPLED X-SEC (N AND O) | 2912 |

DLC0017_01.002 | ANISN LIBRARY ROUTINE (SOURCE) | 140 |

DLC0017_01.003 | SAMPLE PROBLEM DD-CARDS AND DATA | 5 |

DLC0017_01.004 | SAMPLE PROBLEM OUTPUT | 12 |

Keywords: cross sections, data, elastic scattering, gamma radiation, inelastic scattering, multigroup, neutron transport theory.