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

DLC-0041 ZZ-VITAMIN-C.

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

top ]
1. NAME

ZZ-VITAMIN-C.

top ]
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
top ]
3. DESCRIPTION

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

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) 10-5 to 0.125eV

  • 1/E slowing-down spectrum 0.125eV to 820.8 KeV

  • fission spectum 820.8 keV to 10.0 MeV

  • 1/E spectrum 10.0 MeV to 12.57 MeV

  • velocity exponential fusion peak 12.57 to 15.57 MeV

  • 1/E spectrum 15.57 MeV 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 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.

top ]
4. METHODS

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.

top ]
7. UNUSUAL FEATURES

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.

top ]
9. STATUS
Package ID Status date Status
DLC-0041/02 20-JUL-1992 Screened
top ]
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).
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

Oak Ridge National Laboratory

Oak Ridge, TN 37830, USA

top ]
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
top ]
17. CATEGORIES
  • Z. Data

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