1. NAME AND TITLE OF DATA LIBRARY
EPR: Coupled 100-Group Neutron 21-Group Gamma-ray Cross Sections for EPR
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval program is included in the package.
Engineering Physics Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
4. HISTORICAL BACKGROUND AND INFORMATION
The coupled 100 energy group neutron and 21 energy group gamma-ray ANISN-formatted cross
section library was modified by the addition of cross sections and data sets, as was the 100 energy
group master cross section library. These multigroup libraries were generated for use in neutronics
calculations for the conceptual designs of the Experimental Power Reactor (EPR) and other fusion-reactor models.
5. APPLICATION OF THE DATA
The ANISN-formatted cross sections can be used with the one- or two-dimensional discrete
ordinates transport codes ANISN or DOT, respectively, or the Monte Carlo code MORSE. After
further processing by modules of the AMPX system, master cross sections can be used with the multi-dimensional diffusion theory code VENTURE, the sensitivity analysis code SWANLAKE, or the one-dimensional discrete ordinates transport code XSDRNPM.
6. SOURCE AND SCOPE OF DATA
Selected modules of the AMPX system were used to generate data sets for the EPR ANISN-formatted library from the latest ENDF/B-formatted data for fuel, structural, and neutron-absorbing
materials. The fine-group neutron energy structure for the library is the GAM-II 99 epithermal and
fast groups plus a thermal group. The majority of the data sets were for a P8 order of Legendre
expansion. Neutron- and photon-production cross sections were weighted with a 1/E function for En
> 5kT (0.345 eV) and with a Maxwellian distribution peaked at 800 K for En < 5kT. The photon-interaction cross sections were flat weighted. All resonance nuclides were treated as infinitely dilute.
The coupled group cross sections included in DLC-37/EPR are:
Ni, Cr, Fe, 55Mn, 59Co, Cu, 4He, C, O, Al, Pb, 6Li, 7Li, 10B, H, 9Be, V, Nb, 11B, Ti, F, Si, Mg, K,
Na, Na, N, Mo, NatZr, 235U, 238U, 31P, 32S, Sn, Cl, Ca, 10B (n,t)2alpha, 10B (n,alpha), 11B (n,t), 11B
(n,alpha), 6Li (n,t), 7Li (n,n't), 6Li Hot Kerma Factors, Nb, 237Np, 239Pu, 197Au, 182W, 183W, 184W, 186W,
181Ta, 232Th, 232U, D, 9Be, Fe, 6Li, 7Li.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
BCD card images; IBM 360/91.
9. TYPICAL RUNNING TIME
W. E. Ford, III and B. R. Diggs to R. T. Santoro, "Modification No. 18 to the ANISN-formatted EPR Cross-Section Library," Internal Correspondence (May 1978).
W. E. Ford, III and B. R. Diggs to R. T. Santoro, "Modification No. 17 to EPR Cross-Section Libraries," Internal Correspondence (October 1977).
W. E. Ford, III and B. R. Diggs to R. T. Santoro, "Modification No. 16 to EPR 100-218 Cross Section Library," Internal Correspondence (February 17 1977).
W. E. Ford, III, R. T. Santoro, R. W. Roussin, and D. M. Plaster," Modification Number One to the Coupled 100n-218 Cross-Section Library for EPR Calculations," ORNL/TM-5249 (March 1976).
L. R. Williams, "Instructions for LIBGEN, a Code to Convert from Card Image to Binary ANISN
Format," Informal Notes (1972).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one tape cartridge in TAR format which contains the
library, the retrieval program written in Fortran IV and the Output-List file.
12. DATE OF ABSTRACT
KEYWORDS: ANISN FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; CTR NEUTRONICS CROSS SECTIONS; GAM 100-GROUP STRUCTURE; KERMA FACTORS; MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS