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DLC-0027 ZZ-DLC-27B/AMPX01.

ZZ AMPX01/27C, Coupled Neutron-Gamma Group Constant Library by AMPX for Transport Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-DLC-27B/AMPX01(104,22).
126-group coupled neutron and gamma-ray transport cross section data generated by AMPX.
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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
ZZ-AMPX01/27C DLC-0027/01 Tested 01-NOV-1979

Machines used:

Package ID Orig. computer Test computer
DLC-0027/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

  FORMAT:  ANISN, DOT, MORSE

NUMBER OF GROUPS: The neutron energy range (15 MeV to thermal) is described by 104 groups. The gamma-ray energy range (10 MeV to 0.02  MeV) is described by 22 energy groups.

  NUCLIDES: N, O, Al, H, K, Si, Ca, Na, C, and Fe.

ORIGIN: For all materials, except C and K, was the Defense Nuclear  Agency Working Cross Section Library dated September 1972. The K and C data came from ENDF/B-3.

WEIGHTING SPECTRUM: For the neutrons 1/E in the fast range and Maxwellian (300 deg.K) in the thermal range. For the gamma-ray interaction a flat weighting function  was used.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The DLC-27 library was generated for use in albedo studies of neutrons incident on various types of concrete. It is probably also suitable for neutrons, gamma-rays, or coupled neutron and secondary  gamma-ray   transport   through concrete-like materials.It is a coupled set of neutron and gamma-ray cross sections for the elements N, O, Al, H, K, Si, Ca, Na, C, and Fe.
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4. METHOD OF SOLUTION

The AMPX system was utilized to generate the entire coupled library in a single computer run. For all materials except C and K, the basic evaluated data from which the multigroup library was derived was the Defense Nuclear Agency Working Cross Section Library dated September 1972. The K data came from ENDF/B-3. The C was ENDF/B-3 with photon production added to describe a single inelastically and isotropically produced gamma-ray. The neutron energy range (15 MeV to thermal) is described by 104 groups having the same energy structure as used for DLC-9. The gamma-ray energy range (10 MeV to 0.02 MeV) is described by 22 energy groups. For generating the multigroup neutron interaction and gamma-ray production cross sections, the assumption was made that the neutron  flux variation (weighting function) was 1/E in the fast range and Maxwellian (300 deg.K) in the thermal range. For the gamma-ray interaction multigroup cross section generation, a flat weighting function was used. The neutron and gamma-ray scattering processes are represented by a P5 Legendre expansion.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

Using the retrieval program to convert to an unformatted tape requires 48 seconds on the IBM 370/168.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

LIBGEN - is a modified version of the library generation routine available in the ANISN code package.  This version reads the card image AMPX01 tape and converts it into an unformatted library tape for direct use in ANISN, DOT, or MORSE.
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9. STATUS
Package ID Status date Status
DLC-0027/01 01-NOV-1979 Tested at NEADB
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10. REFERENCES

- J.E. White:
104N-22G Coupled Neutron and Gamma-Ray Library Generated with AMPX    Informal Notes (1973).
- L.R. Williams:
  Input Description for LIBGEN
  Informal Notes (1972).
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0027/01 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The current version of the library is dated September 1973.
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15. NAME AND ESTABLISHMENT OF AUTHOR

Computer Science Division
Union Carbide Corporation
and
Neutron Physics Division
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.
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16. MATERIAL AVAILABLE
DLC-0027/01
File name File description Records
DLC0027_01.001 INFORMATION 5
DLC0027_01.002 SOURCE (F4,EBCDIC) 143
DLC0027_01.003 LIBRARY 17032
DLC0027_01.004 JCL 61
DLC0027_01.005 SAMPLE PROBLEM INPUT 1
DLC0027_01.006 SAMPLE PROBLEM OUTPUT 60
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: ENDF/B, concretes, cross sections, data, gamma radiation, multigroup, neutrons, shielding, transport theory.