Computer Programs
DLC-0017 ZZ-NOX.
last modified: 01-APR-1973 | catalog | categories | new | search |

DLC-0017 ZZ-NOX.

ZZ NOX, 119-Group Coupled Cross-Section of Nitrogen, Oxygen, Air for MORSE

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1. NAME

ZZ-NOX.

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2. COMPUTERS
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Program name Package id Status Status date
ZZ-NOX 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. DESCRIPTION

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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/NOX 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 CCC-82/ANISN-CEA, CCC-89/DOT, or CCC-127/MORSE.

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4. METHODS

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 PSR-13/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 CCC-128/O6R, but modifications had to be made to the version in the RSIC code package to generate the desired gamma-ray production matrices.

 

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 0.02 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. These are available from RSIC upon request.

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6. TYPICAL RUNNING TIME

To read the NOX data from a card image tape and rewrite it on an unformatted tape required 14 seconds on the IBM 360/91 computer.

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8. RELATED OR AUXILIARY PROGRAMS

LIBGEN is a modified version of the library generation routine which is available in the ANISN code package. This version will read data from a card image tape, the mode by which NOX is distributed, and write an unformatted tape for direct use with ANISN.

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9. STATUS
Package ID Status date Status
DLC-0017/01 01-APR-1973 Tested at NEADB
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10. REFERENCES
  • P. G. Young and D. G. Foster, Jr., "An Evaluation of the Neutron and Secondary Gamma-Ray Production Cross Sections for Nitrogen," LA-4725 (1972).

  • P. G. Young and D. G. Foster, Jr., "An Evaluation of the Neutron and Secondary Gamma-Ray Production Cross Sections for Oxygen," LA-4780 (1972).

  • R. W. Roussin, "The Defense Nuclear Agency Working Cross Section Library: Description and Contents," ORNL-RSIC-34 (1972).

DLC-0017/01, included references:
- E. A. Straker and B. J. McGregor, "A Calculation of Gamma-Ray Production and
Transport in Liquid Nitrogen," ORNL-TM-3635 (December 1971).
- "LIBGEN: A Special Version of the ANISN Library Generation Routine which
Converts a Card Image FIDO Format Cross Section Tape into an Unformatted ANISN
Library Tape."
- 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,
SAI-71-550-LJ (March 1972).
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The cross-section data in DLC-17/NOX were compiled at ORNL to be used for studies of neutron and secondary gamma-ray transport in nitrogen and air. The data library was preserved since it was based on new evaluations for N and O and since results using the data have been reported. The nitrogen data were used in a calculation study of gamma-ray production and transport in liquid nitrogen which compared results with experiments in liquid nitrogen. Results of several ORNL studies using the nitrogen and oxygen data were presented to assess the adequacy of the nitrogen cross sections.

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15. NAME AND ESTABLISHMENT OF AUTHORS

Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.

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16. MATERIAL AVAILABLE
DLC-0017/01
File name File description Records
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
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17. CATEGORIES
  • Z. Data

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