RSICC Home Page
RSIC DATA LIBRARY DLC-053

1. NAME AND TITLE OF DATA LIBRARY

VITAMIN-4C: 171 Neutron Group Cross Sections and Bondarenko Factors in CCC Interface Formats for Fusion and LMFBR Neutronics.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is in the package.

3. CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

4. HISTORICAL BACKGROUND AND INFORMATION

VITAMIN-4C is a program for the development, generation, validation and distribution of a general purpose, processed multigroup cross section library (PMCSL) for use in CTR neutronics studies. RSIC coordinated an effort to establish the CTR-PMCSL based on input requirements specified by ERDA-DCTR contractors. It was possible to define a single 171 neutron, 36 gamma-ray group cross-section library useful for both CTR and LMFBR neutronics analysis. The master library was generated using the MINX neutron processor and the gamma-ray processor from the AMPX system.

5. APPLICATION OF THE DATA

DLC-53/VITAMIN-4C contains neutron cross sections essentially equivalent to DLC-41B/VITAMIN-C. The data in CCCC format were removed from the original version of DLC-41 and placed in DLC-53; DLC-53 contains only data in the CCCC format. Both are the result of a Department of Energy Divisions of Magnetic Fusion Energy and Reactor Research and Technology collaboration to produce cross section libraries for fusion and LMFBR neutronics.

6. SOURCE AND SCOPE OF DATA

DLC-53/VITAMIN-4C contains 171 neutron group cross sections and Bondarenko factors in CCCC Interface Format. They are in ISOTXS Format and in BRKOXS format. The ISOTXS format is as follows:

Mo, 241Am, 238Pu, 241Pu, 9Be, 23Na, Ca, Fe, 235U, 238U, 239Pu, K, C, H, 11B, 27Al, Si, 240Pu, 236U, Ni, 55Mn, Cr, 16O, 234U, 242Pu, 93Nb, 6Li, 7Li, Pb, 14N, Mg, 2H, V, F, Cu, 10B, 3H, 3He, 4He, 31P, 32P, Cl, Ti, 59Co, Zircalloy, Zr, 107Ag, 109Ag, Cd, Sn, Ba, 151Eu, 153Eu, 181Ta, 182W, 183W, 184W, 186W, 232Th, 233U, 237Np.

The Neutron Group Bondarenko Factors in BRKOXS Format are as follows:

Mo, 241Am, 238Pu, 241Pu, 9Be, 23Na, Ca, Fe, 235U, 238U, 239Pu, K, C, H, 11B, 27Al, Si, 240Pu, 236U, Ni, 55Mn, Cr, 16O, 234U, 242Pu, 93Nb, 6Li, 7Li, Pb, 14N, Mg, 2H, V, F, Cu, 10B, 3H, 3He, 4He, 31P, 32P, Cl, Ti, 59Co, Zircalloy, Zr, 107Ag, 109Ag, Cd, Sn, Ba, 151Eu, 153Eu, 181Ta, 182W, 183W, 184W, 186W, 232Th, 233U, 237Np.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

Card images; IBM-360/91. (D00053I369100)

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

R. W. Roussin, C. R. Weisbin, J. E. White, N. M. Greene, R. Q. Wright, and J. B. Wright, "The CTR Processed Multigroup Cross Section Library for Neutronics Studies," ORNL/RSIC-37.

R. W. Roussin and D. B. Simpson, "Sample Problems for DLC-53/VITAMIN-4C," Prepared for Presentation at the RSIC Workshop on Multigroup Cross-Section Handling Codes (March 1978).

11. CONTENTS OF LIBRARY

Included are the referenced documents and either one DC6150 tape cartridge in TAR format or 8 DS/HD 3.5-in. (1.44 MB) diskettes in self-extracting compressed DOS files, which contains the neutron group cross sections, the Bondarenko factors, JCL to compile and assemble the AMPX-II subroutine library, JCL and input data for the infinite medium problem and the standard blanket problem, plus output from the sample problems.

12. DATE OF ABSTRACT

December 1984.

KEYWORDS: CCCC INTERFACE FORMAT; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS