Computer Programs
DLC-0119 ZZ-HILO86.
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DLC-0119 ZZ-HILO86.

ZZ HILO86, 66 Neutron, 22 Gamma Group Cross-Section Library for ANISN, DORT, MORSE

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-HILO86.
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2. COMPUTERS
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-HILO86 DLC-0119/01 Tested 20-APR-1994

Machines used:

Package ID Orig. computer Test computer
DLC-0119/01 PC-80386 PC-80486
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3. DESCRIPTION OF PROGRAM OR FUNCTION


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

  FORMAT: ANISN, DORT, MORSE

  NUMBER OF GROUPS: 66 Neutron, 22 Gamma-Ray

NUCLIDES: H, B-10, B-11, C, N, O, Na, Mg, Al, Si, S, K, Ca, Cr, Fe  Ni, W, Pb.

  ORIGIN: ENDF/B-IV + ENDF/B-V

  WEIGHTING SPECTRUM: 1/E used for neutron energies >/ 19.6 MeV

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
For a variety of applications (accelerator shielding, the use of neutrons in radiotherapy, radiation damage studies, etc.) it is necessary to carry out transport calculations involving medium-energy neutrons. ZZ-HILO86 is a group cross section library with 66 Neutron, 22 Gamma-Ray groups for Neutron Energies up to 400 MeV, in the form needed for the CCC-254/ANISN-ORNL and CCC-484/DORT discrete ordinates codes and for the CCC-474/MORSE-CGA Monte Carlo code.
Below 19.6 MeV, the library consists of data derived from DLC-113/VITAMIN-E (ENDF/B-IV) except for sulfur and lead. Above that energy, differential elastic cross section data have been chosen so that the total, i.e., elastic + nonelastic, cross sections agree with experimental data. The library is P5. Data are provided for: H, 10B, 11B, C, N, O, Na, Mg, Al, Si, S, K, Ca, Cr, Fe, Ni, W, Pb.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

On a PC 386, the program BCD2BIN converted the HILO86 BCD data into binary form in about 7 minutes.
DLC-0119/01
NEA-DB executed the test case of the ASCII-to-binary conversion program on a 66-MHz PC/80486 in 40 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

   BCBN: Converts ANISN card-image data to binary format.
This cross-section library for multigroup transport calculations for neutron and photon energies up to 400 MeV and 20 MeV, respectively,  is an upgrade of a similar library, DLC-41/VITAMIN-C (ENDF/B-IV).
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9. STATUS
Package ID Status date Status
DLC-0119/01 20-APR-1994 Tested at NEADB
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10. REFERENCES

- H. Kotegawa et al.:
  Attenuation Data of Point Isotropic Neutron Sources up to 400 MeV
  in Water, Ordinary Concrete and Iron
  JAERI-Data/Code 94-003 (August 1994)
DLC-0119/01, included references:
- R.G. Alsmiller, Jr., J.M. Barnes and J.D. Drischler:
  Neutron Photon Multigroup Cross Sections for Neutron Energies Less
  Than or Equal to 400 MeV (Revision 1)
  ORNL/TM-9801 (Feb. 1986).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
DLC-0119/01
The conversion program was executed at NEA-DB under MS-DOS version 6.2. The source code was compiled with the Lahey F77L-EM/32 compiler version 5.11.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
                Battelle, Columbus, Ohio, USA
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16. MATERIAL AVAILABLE
DLC-0119/01
File name File description Records
DLC0119_01.001 Information file 105
DLC0119_01.002 BCD to BINARY FORTRAN 77 source program 48
DLC0119_01.003 Executable program 0
DLC0119_01.004 IBM mainframe JCL 19
DLC0119_01.005 Output file (HILO86.OUT) 108
DLC0119_01.006 Cross sections for neutron energies library 32385
DLC0119_01.007 DOS file-names 6
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: albedo, coupled neutron gamma cross sections, multigroup, neutron cross sections, photon transport.