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DLC-0130 ZZ-DABL69.

ZZ DABL69, 46-Group Neutron, 23-Group Gamma Cross-Section in ANISN Format from ENDF/B-V

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-DABL69.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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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3. DESCRIPTION OF PROGRAM OR FUNCTION



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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.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:  Not applicable.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

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.
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9. STATUS
Package ID Status date Status
DLC-0130/01 31-MAY-2001 Masterfiled Arrived
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10. REFERENCES

- 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).
DLC-0130/01, included references:
- Notes on Contents of DLC-130/DABL-69 (November 22, 1993).
- D.T. Ingersoll et al.:
  DABL69 - A Broad-Group Neutron/Photon Cross-Section Library for
  Defense Nuclear Applications
  ORNL/TM-10568 (June 1989).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0130/01 FORTRAN
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
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16. MATERIAL AVAILABLE
DLC-0130/01
symb data lib    mag tapedabl.dat 46 Neutron, 23 G-Ray. P5, X-Sects LBSTP
source program   mag tapebcbn.f BCBN - BCD to binary conversion     SRCTP
test-case data   mag tapebcbn.jcl JCL for BCD to binary conversion  DATTP
test-case output mag tapebcbn.out Printed output from the BCBN prog.OUTTP
prog. note               Notes on Contents of DABL-69 (Nov.22, 1993)NOTPT
report                   ORNL/TM-10568 (June 1989)                  REPPT
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: data library, multigroup, shielding.