Computer Programs
DLC-0008 ZZ-BP-3, ZZ-BP-6.
last modified: 17-AUG-1992 | catalog | categories | new | search |

DLC-0008 ZZ-BP-3, ZZ-BP-6.

ZZ BP-3, 104-Group Neutron Cross-Section Library for Transport Calculation
ZZ BP-6, 104 Group Neutron and Gamma-Ray Multigroup Cross-Section Library for Transport Calculation

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1. NAME

ZZ-BP-3, ZZ-BP-6.

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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-BP-3 DLC-0008/01 Tested 17-AUG-1992
ZZ-BP-6 DLC-0008/02 Tested 17-AUG-1992

Machines used:

Package ID Orig. computer Test computer
DLC-0008/01 DEC VAX 8810
DLC-0008/02 DEC VAX 8810
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3. DESCRIPTION
  • ZZ-BP-3 - 22 Neutron, 18 Gamma-Ray Group Cross Sections for Air, Generated by CSP from ENDF/B.

  • ZZ-BP-6 - 22 Neutron, 18 Gamma-Ray Group Cross Sections for H, 10B, and 12C, Generated by SUPERTOG and ANISN from ENDF/B.

 

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SPECIFIED ON ORNL-RSIC-25, SHIELDING BENCHMARK PROBLEMS

 

BP-3 (Neutron cross sections)

FORMAT: ANISN, DOT and MORSE

NUMBER OF GROUPS: 22 neutron / 18 gamma-ray

NUCLIDES: air

ORIGIN: ENDF/B

WEIGHTING SPECTRUM: 1/E

 

BP-6 (neutron and gamma-ray cross sections)

FORMAT: ANISN, DOT and MORSE

NUMBER OF GROUPS: 22 neutron / 18 gamma-ray

NUCLIDES: Borated Polyethylene (C-12, H, and B-10)

ORIGIN: ENDF/B-II

WEIGHTING SPECTRUM:

 

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The cross section data can be used to repeat the Shielding Benchmark Problems 3.0 and 6.0 for testing against the results published in ORNL-RSIC-25.

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4. METHODS

ZZ-BP-3 neutron cross sections from the CCC-17/05R library were processed into 104 neutron groups using the PSR-9/CSP code. The fine-group neutron cross sections were collapsed to 22 broad groups using CCC-254/ANISN with an equilibrium fission spectrum source. The resulting multigroup cross sections are P5 coefficients punched on cards in format suitable for input to ANISN, DOT, and MORSE.

 

ZZ-BP-6 neutron and gamma-ray cross sections for 12C, H, and 10B were from ENDF/B-II data. The neutron multigroup cross sections were generated into 104 neutron groups using the PSR-13/SUPERTOG code. The fine-group neutron cross sections were collapsed to 22 broad groups using CCC-254/ANISN with an equilibrium fission spectrum source. The gamma-ray multigroup cross sections were generated using PSR-7/MUG. The neutron-gamma-ray coupling utilized yield data from the DLC-12/POPOP4 library (data sets 010101, 060101, 060301, and 05100201). The neutron-gamma-ray coupled multigroup cross-section set was generated using the SAMPLE COUPLING CODE (ASCC). The multigroup cross sections are in a 22-18 group structure with P3 coefficients punched on cards in format suitable for input to ANISN, DOT, and MORSE.

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9. STATUS
Package ID Status date Status
DLC-0008/01 17-AUG-1992 Screened
DLC-0008/02 17-AUG-1992 Screened
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10. REFERENCES
  • C.E. Burgart: SHIELDING BENCHMARK PROBLEM 6.0: Neutron and Gamma-Ray Fluence Transmitted through a Slab of Borated Polyethylene ORNL-RSIC-25 (December 1973).

DLC-0008/01, included references:
- E.A. Straker:
  SHIELDING BENCHMARK PROBLEM 3.0: Neutron Spectrum from
  Point Fission and 14 MeV Sources in Infinite Air.
  ORNL-RSIC-25  (December 1968)
DLC-0008/02, included references:
- E.A. Straker:
  SHIELDING BENCHMARK PROBLEM 3.0: Neutron Spectrum from
  Point Fission and 14 MeV Sources in Infinite Air.
  ORNL-RSIC-25  (December 1968)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Oak Ridge National Laboratory

Oak Ridge, TN, USA

 

Science Applications, Inc.

Albuquerque, NM, USA

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16. MATERIAL AVAILABLE
DLC-0008/01
File name File description Records
DLC0008_01.001 Information file 30
DLC0008_01.002 ZZ-BP-3 data library 124
DLC-0008/02
File name File description Records
DLC0008_02.001 Information file 26
DLC0008_02.002 ZZ-BP-6 data library (formatted) 685
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17. CATEGORIES
  • Z. Data

Keywords: coupled neutron gamma cross sections, data library, multigroup, shielding.