1. NAME AND TITLE OF DATA LIBRARY
VITAMIN-E: 174n, 38g Cross-Section Library in AMPX Format.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM
No retrieval program is provided. The PSR-117/MARS or PSR-63/AMPX code packages are suggested for full implementation of the capabilities of VITAMIN-E. JCL and sample input are provided to execute sample problems using MARS.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
The successful application of DLC-41/VITAMIN-C, based on ENDF/B-IV, to a variety of radiation transport problems led to the development of specifications for an ENDF/B-V based cross-section library, denoted VITAMIN-E.
5. APPLICATION OF THE DATA
The early phases of this new cross-section library were focused on materials for fast reactor applications and were applied to benchmark testing of ENDF/B-V. More recently, requests have been made for additional materials to be added to the basic library for fusion and weapons radiation transport applications. The library is expected to perform well for radiation transport problems where thermal upscatter is not important.
6. SOURCE AND SCOPE OF DATA
The energy structure of VITAMIN-E contains 174 neutron and 38 gamma-ray groups and includes the 171 neutron and 36 photon groups of VITAMIN-C as a subset. The group structure has fine detail in the energy region where cross section minima occur for important shielding materials. The 174 neutron group data were processed with MINXI5; the 174 neutron, 38 photon group data were processed with LAPHNGAS (AMPX III); and the 38 gamma-ray group data with SMUG (AMPX III) from DLC-99/HUGO. The ENDF/B-V special purpose dosimetry, activation, and gas production files have also been processed into the VITAMIN-E group structure using XLACS2, NITAWL, and WORM.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
PSR-117/MARS can be used to translate the data into binary form and to perform a variety of useful manipulations including checking, editing, self shielding, and group collapsing.
8. DATA FORMAT AND COMPUTER
Card images; IBM 3033 D00113I303301).
9. TYPICAL RUNNING TIME
The first part of the ZPR 6/7 infinite medium problem required approximately 55,000 I/O's and 10.5 cpu minutes on the IBM 3033. This includes the 20,000 I/O's and 9 cpu minutes required to convert the formatted library to binary. The XSDRNPM run required only 37 cpu seconds and 6065 I/O's, and the GIP/ANISN run took 10,060 I/O's and 38 cpu seconds. The first part of the CTR standard blanket run required 58,066 I/O's and 10.15 cpu minutes. The XSDRNPM problem ran for 1.3 cpu minutes using 5147 I/O's while the GIP/ANISN run required 1.16 cpu minutes and 9160 I/O's.
R. W. Roussin et al., "VITAMIN-E: A Coupled 174 Neutron, 38 Gamma-Ray Multigroup Cross- Section Library for Deriving Application Dependent Working Libraries for Radiation Transport Calculations," Draft ORNL-RSIC Report (November 1987).
11. CONTENTS OF LIBRARY
The 174n group transport cross section data are separated into six files; the 174n, 38g group photon production data and the 38g group photon transport data are each included in separate files. Special purpose neutron dosimetry, activation, and gas production data files are also provided. JCL is included to execute sample problems using MARS. One DC6150 cartridge tape in TAR format is required to obtain the entire package.
12. DATE OF ABSTRACT
July 1984; December 1984, August 1985, November 1987.
KEYWORDS: AMPX INTERFACE FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; CTR NEUTRONICS CROSS SECTIONS; CTR PROCESSED CROSS-SECTION LIBRARY; GAMMA-RAY CROSS SECTIONS; GAMMA-RAY PRODUCTION DATA; MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS; REACTION CROSS SECTIONS