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 OR DESIGNATION OF PROGRAM:  ZZ-BP-3, ZZ-BP-6.
(A) ZZ-BP-3 - 22 Neutron, 18 Gamma-Ray Group Cross Sections for Air,               Generated by CSP from ENDF/B.
(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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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-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 OF PROGRAM OR FUNCTION


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

  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:

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

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. METHOD OF SOLUTION

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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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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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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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:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

          Oak Ridge National Laboratory
          Oak Ridge, Tennessee

          Science Applications, Inc.
          Albuquerque, New Mexico
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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
  • J. Gamma Heating and Shield Design
  • Z. Data.

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