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

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.

3. DESCRIPTION OF PROGRAM OR FUNCTION


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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.

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

6. TYPICAL RUNNING TIME:

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:

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).

- 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)
- 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)

11. MACHINE REQUIREMENTS:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHORS

          Oak Ridge National Laboratory
          Oak Ridge, Tennessee

          Science Applications, Inc.
          Albuquerque, New Mexico

File name	File description	Records
DLC0008_01.001	Information file	30
DLC0008_01.002	ZZ-BP-3 data library	124

File name	File description	Records
DLC0008_02.001	Information file	26
DLC0008_02.002	ZZ-BP-6 data library (formatted)	685