DLC-0041: ZZ VITAMIN-C/B, 171 Neutron-Group, 36 Gamma-Group Coupled Cross-Section for Fusion, LMFBR Calculations

[Program Service | Recent programs]

DLC-0041 ZZ-VITAMIN-C/B. (Abstract last modified 20-JUL-1992)

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

Abstract Table of Contents:

1. NAME OR DESIGNATION OF PROGRAM - ZZ-VITAMIN-C/B.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status ZZ-VITAMIN-C/B DLC-0041/01 Obsolete ZZ-VITAMIN-C DLC-0041/02 Tested

Machines used: Package-ID Orig.Computer Test Computer DLC-0041/02 IBM 360/91 DEC VAX 8810

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.

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -

6. TYPICAL RUNNING TIME -

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.

8. RELATED AND AUXILIARY PROGRAMS -

9. STATUS
DLC-0041/01: 12-MAR-1992 Obsolete
DLC-0041/02: 20-JUL-1992 Screened

10. REFERENCES  -
DLC-0041/02:
- 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).

11. MACHINE REQUIREMENTS -

12. PROGRAMMING LANGUAGE(S) USED -
DLC-0041/02:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED -

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHOR -
Oak Ridge National Laboratory
Oak Ridge
Tennessee 37830, USA

17. CATEGORIES  -

- C.  Static Design Studies
- X.  Magnetic Fusion Research
- Z.  Data.

Keywords: CROSS SECTIONS, DATA, FUSION REACTORS, GAMMA SPECTRA, GROUP CONSTANTS, LMFBR REACTORS, NEUTRON SPECTRA