Computer Programs
DLC-0041 ZZ-VITAMIN-C/B.
last modified: 20-JUL-1992 | catalog | categories | new | search |

DLC-0041 ZZ-VITAMIN-C/B.

ZZ VITAMIN-C/B, 171 Neutron-Group, 36 Gamma-Group Coupled Cross-Section for Fusion, LMFBR Calculations

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-VITAMIN-C/B.
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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-VITAMIN-C DLC-0041/02 Tested 20-JUL-1992

Machines used:

Package ID Orig. computer Test computer
DLC-0041/02 IBM 360/91 DEC VAX 8810
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3. DESCRIPTION OF PROBLEM OR FUNCTION


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

  FORMAT: AMPX, CCCC format.

  NUMBER OF GROUPS: 171 neutron, 36 gamma-ray group cross section

NUCLIDES: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zr, Nb, Mo, Ag, Cd, Sn, Eu, Ta, W, Pb, Th, U, Pu, Am

  ORIGIN: ENDF/B

WEIGHTING SPECTRUM: - Maxwellian thermal spectrum (300K) up to 0.125eV
                      - 1/E slowing down spectrum to 820.8 KeV
                      - fission spectum to 10.0 MeV
                      - 1/E spectrum to 12.57 MeV
- velocity exponential fusion peak to 15.57MeV                       - 1/E spectrum to 17.333 MeV.
Gamma cross sections are flat-weighted.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
ZZ-VITAMIN-C/B is a data library containing 171 neutron, 36 gamma-ray group cross section data for fusion and LMFBR neutronics.
The weighting function for the neutron data consists of six regions: a Maxwellian thermal spectrum (300K) up to 0.125 eV, a 1/E  slowing down spectrum to 820.8 KeV, a fission spectum to 10.0 MeV, a 1/E spectrum to 12.57 MeV, a velocity exponential fusion peak to 15.57 MeV, and a 1/E spectrum to 17.333 MeV. The gamma cross sections are flat-weighted.
The Legendre expansion order is P3. Data are available in the form of a 171 neutron group AMPX interface, a 171 neutron 36 gamma-  ray production AMPX interface, and a 36 group gamma-ray interaction  AMPX interface. The neutron data are also available in CCCC format as ISOTXS neutron cross section and BRKOXS self-shielding factor standard interface files.
Data exists for 60 nuclides used in proposed fusion or fission/ fusion hybrid systems.
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4. METHOD OF SOLUTION

The data has been computed from ENDF/B files using the program MINX. The Bondarenko method is employed to create  group dependent resonance self-shielding factors to account for temperature and dilution effects.
The fractional error tolerances were set to 0.5 percent, and 0.1 percent for integration.
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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

The AMPX and CCCC interface formats allow the user to perform self-shielding and group collapsing to format a problem dependent library for his own use.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
DLC-0041/02 20-JUL-1992 Screened
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10. REFERENCES:
DLC-0041/02, included references:
- R.W. Roussin, C.R. Weisbin, J.E. White, N.M. Greene, R.Q. Wright,
  J.B. Wright:
  The CTR Processed Multigroup Cross Section Library for Neutronics
  Studies
  ORNL/RSIC-37.
- R.W. Roussin, D.B. Simpson:
  Sample Problems for DLC-41/VITAMIN-C Presented at the RSIC Work
  shop on Multigroup Cross-Section Handling Codes
  (March 1978).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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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 AUTHOR

Oak Ridge National Laboratory
Oak Ridge
Tennessee 37830, USA
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16. MATERIAL AVAILABLE
DLC-0041/02
File name File description Records
DLC0041_02.001 Information file 70
DLC0041_02.002 171 neutron group xsecs (21 materials) 163883
DLC0041_02.003 36 photon interaction xsecs (42 materials) 20833
DLC0041_02.004 171 neutron group xsecs (20 materials) 185053
DLC0041_02.005 171 neutron-36 gamma coupled group xsecs 33005
DLC0041_02.006 171 neutron group xsecs (25 materials) 98685
DLC0041_02.007 GIP source program 1684
DLC0041_02.008 ANISN source program 4026
DLC0041_02.009 JCL to compile & assemble AMPX-II subr. lib 31
DLC0041_02.010 JCL & input data for AIM 29
DLC0041_02.011 JCL & input data for AJAX,BONAMI,RADE,.. 254
DLC0041_02.012 JCL & input data for GIP & ANISN 103
DLC0041_02.013 JCL & input data for AIM & CHOX 93
DLC0041_02.014 JCL & input data for RADE,DIAL,MALOCS 122
DLC0041_02.015 JCL & input data for NITAWL, XZSDRNPM 130
DLC0041_02.016 JCL & input data for GIP, ANISN 84
DLC0041_02.017 Output from AIM (BCD AMPX) 66
DLC0041_02.018 Output from AJAX 77
DLC0041_02.019 Output from BONAMI 2415
DLC0041_02.020 Output from RADE 857
DLC0041_02.021 Output from NITAWL (see file 14) 240
DLC0041_02.022 Output from XSDRNPM 904
DLC0041_02.023 Output from GIP 293
DLC0041_02.024 Output from ANISN 991
DLC0041_02.025 Output from AIM (BCD AMPX LAPHNGAS) 66
DLC0041_02.026 Output from AIM (BCD AMPX SMUG) 66
DLC0041_02.027 Output from CHOX 92
DLC0041_02.028 Output from RADE 972
DLC0041_02.029 Output from DIAL 1359
DLC0041_02.030 Output from MALOCS 436
DLC0041_02.031 Output from NITAWL (see file 25) 175
DLC0041_02.032 Output from XSDRNPM (CTR standard blanket) 2255
DLC0041_02.033 Output from GIP (CTR standard blanket) 248
DLC0041_02.034 Output from ANISN (CTR standard blanket) 2125
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17. CATEGORIES
  • C. Static Design Studies
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: LMFBR reactors, cross sections, data, fusion reactors, gamma spectra, group constants, neutron spectra.