Computer Programs

DLC-0119 ZZ-HILO86.

DLC-0119 ZZ-HILO86.

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

NAME, COMPUTER, PROBLEM, CPU, AUXILIARIES, STATUS, REFERENCES, LANGUAGE, OPERATING SYSTEM, AUTHOR, MATERIAL, CATEGORIES

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1. NAME

ZZ-HILO86.

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2. COMPUTERS

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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, 10B, 11B, 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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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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8. RELATED OR 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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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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13. SOFTWARE REQUIREMENTS

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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15. NAME AND ESTABLISHMENT OF AUTHORS

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

Z. Data

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