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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. Only liaison officers are authorised to submit online requests. Rules for requesters 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


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  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

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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 item found

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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.