1. NAME AND TITLE OF DATA LIBRARY
VELM61 and VELM22: Multigroup Cross-Section Libraries based on ENDF/B-V data for Sodium-Cooled Reactor Shield Analysis.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM
BCBN: A program to convert ANISN card-image data to binary format.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
This data package grew out of a need to upgrade the previously undocumented (51n,25g) cross section library used for shielding analysis work associated with liquid metal reactor systems. In addition to the economic benefit, reference broad-group libraries avoid duplicated efforts among national program participants and assure a common database for design analyses. The energy group structures (61n,23g) and (22n,10g) are subsets of the VITAMIN-E group structure and are tailored to the iron and sodium resonances, windows, and capture gamma-ray spectra.
5. APPLICATION OF THE DATA
Though the libraries were specifically designed for sodium-cooled reactor shield analysis, part of the data is general enough for most other purposes until more appropriate problem-dependent cross-section libraries based on ENDF/B-V are available. For example, the cross sections generated using the standard and 1/(E Sigt) weighting functions are largely problem independent. The (22n,10g) library is recommended for scoping calculations of a new problem with the (61n,23g) library used for final results. This should be easy to accomplish since the cross-section sets in both libraries have the same contents and identifications. Any computer code requiring multigroup cross sections can use the data.
6. SOURCE AND SCOPE OF DATA
Eighty-one materials from the DLC-113B/VITAMIN-E library which were available on August 20,1985 are included as a first part of the VELM libraries. These materials were collapsed using the AMPX code system with the VITAMIN-E weighting functions. The second part of the VELM libraries contains 33 additional shielding materials such as Na, Fe, and steel using problem-dependent weighting functions generated by ANISN analysis of a typical problem. VELM61 contains 61 neutron and 23 gamma-ray energy groups. The corresponding energy group structure for VELM22 is 22 and 10. The Legendre order of expansion for angular distribution is 5.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
Card images; IBM 360/370.
9. TYPICAL RUNNING TIME
a. Included in documentation:
C.Y. Fu and D.T. Ingersoll, VELM61 and VELM22: Multigroup Cross-Section Libraries for Sodium-Cooled Reactor Shield Analysis, ORNL/TM-10302 (April 1987).
b. Background information:
C.Y. Fu and D.T. Ingersoll, "Group Structure and Weighting Function Effects on Neutron Penetration Through Thick Sodium-Iron Shields," Proceedings of the Topical Conference on Theory and Practices in Radiation Protection and Shielding, April 22-24, 1987, Knoxville, Tennessee.
C.R. Weisbin, R.W. Roussin, J.J. Wagschal, J.E. White, and R.Q. Wright, Vitamin-E: An ENDF/B-V Multigroup Cross Section Library for LMFBR Core and Shield, LWR Shield, Dosimetry and Fusion Blanket Technology, ORNL-5505 (ENDF-274) (1979).
Radiation Shielding Information Center Data Package DLC-113/VITAMIN-E, A Coupled 174-Neutron, 38-Gamma-ray Multigroup Cross-Section Library for Deriving Application-Dependent Working Libraries for Radiation Transport Calculations, contributed by Oak Ridge National Laboratory.
11. CONTENTS OF LIBRARY
Included is the referenced document in (10.a) and 1 tape cartridge in tar format which contains the cross sections and retrieval program.
12. DATE OF ABSTRACT
KEYWORDS: MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS; ANISN FORMAT; DETECTOR RESPONSE; AMPX INTERFACE FORMAT