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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-DABL69 | DLC-0130/01 | Arrived | 31-MAY-2001 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| DLC-0130/01 | IBM 360 series |
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FORMAT: ANISN
NUMBER OF GROUPS: 46 neutron, 23 gamma-ray
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Y, Zr, Nb, Mo, Cd, Sn, I, Cs, Ba, Gd, Hf, Ta, W, Re, Pt, Au, Pb, Bi, Th, Pa, U, Np, Pu, Am, and Cm.
ORIGIN: ENDF/B-V (VITAMIN-E)
WEIGHTING SPECTRUM: VITAMIN-E weighting functions
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Based on ENDF/B-V data and a revaluation of Fe (MOD 3) which contains significant improvements, this library consists of 80 nuclides that can be used to solve typical calculations of interest to the DNA radiation transport community. Any computer code requiring multigroup cross sections can use the data.
Eighty materials from the DLC-113C/VITAMIN-E library which were available on October 30, 1987 are included as a first part of the DABL69 library. These materials were collapsed using the AMPX code system with the VITAMIN-E weighting functions. The second part of the DABL69 library contains 8 additional materials including N-14, O-16, and steel using problem-dependent weighting functions generated by ANISN of a typical problem. DABL69 contains 46 neutron and 23 gamma-ray energy groups. The Legendre order of expansion for angular distribution is 5.
As in DLC-31, the neutron groups are tailored to allow for the major peaks and valleys in the total neutron cross sections of nitrogen, oxygen, silicon, and iron. On the other hand, the gamma-ray groups are tailored to allow accurate calculation of pair production, annihilation photon transport, hydrogen capture and backscatter photon transport. In the neutron energy range 0.2 to 1.8 MeV, additional boundaries were added to the parent DLC-031 group structure to give better resolution in the region where the largest fraction of the total KERMA frequently occurs.
Source spectra and response functions useful in radiation transport applications are included in the library. Elemental KERMA factors are provided for nuclides ranging from H-1 to Am-243. Version A (D00130/I0360/00) includes card-image data files in both ANISN format and AMPX master format with KERMA factor data derived from DLC-060/MACKLIB-IV.
Version B (D00130/I0360/01) is available in ANISN card images in which the KERMA factor data has been replaced with data derived from DLC-160/KAOS-LIB/V.
BCBN: Convert ANISN card-image data to binary format.
This data package was developed to supersede the DLC-31/FEWG1 cross section library which has been used for Defense Nuclear Agency radiation transport calculations. The availability of ENDF/B-V data coupled with some evidence that the original group structure needed some refinement, provided the driving force in the development of a replacement for FEWG1 which is based on ENDF/B-V.
The energy group structure (46n,23g) is a subset of the VITAMIN-E group structure and is tailored to air-over-ground environments.
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, Dosimetry and Fusion Blanket Technology ORNL-5505 (ENDF-274)(1979).
Radiation Shielding Information Center Data Package DLC-113C/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.
Radiation Shielding Information Center Data Package DLC-160/KAOS-LIB-V, A Library of Nuclear Response Functions Generated by KAOS-V Code from ENDF/B-V and Other Data Files (March 1991).
Keywords: data library, multigroup, shielding.
