last modified: 27-APR-1983 | catalog | categories | new | search |

DLC-0023 ZZ-DLC-23E/CASK.

ZZ DLC-23F CASK, 40-Group Neutron and Gamma Coupled Cross-Section for PWR Shipping Casks

top ]
1. NAME OR DESIGNATION OF PROGRAM:  ZZ-DLC-23E/CASK. 40-group coupled neutron and gamma-ray cross section data.
top ]
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-CASK/F DLC-0023/03 Tested 27-APR-1983

Machines used:

Package ID Orig. computer Test computer
DLC-0023/03 IBM 370/168 IBM 370/168
top ]
3. NATURE OF PHYSICAL PROBLEM SOLVED

  FORMAT: ANISN, DOT, MORSE

  NUMBER OF GROUPS: 40 group set.

NUCLIDES: H, Be, B-10, C, N, O, Na, Mg, Al, Si, K, Ca, Ti, Cr, Mn,  Fe,  Ni, Cu, Mo, Ta, W, Pb, U-235, U-238, Pu-239, and Pu-240.

ORIGIN: ENDF/B-2 library, although some data were taken from other   sources.

  WEIGHTING SPECTRUM: Representative of a water-uranium mixture.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The data were designed for use in shielding analysis of PWR depleted uranium shipping casks. Results of such an analysis are given in ref. 2. The data were collapsed from a fine group structure using a  weighting function representative of a water-uranium mixture (3). Thus, the application of this data for problems not similar to the shipping cask type should be done with caution.
The library was compiled for several elements that are commonly used for shielding calculations. The coupled P3 cross sections are given in the ANISN format which permits their usage in the discrete  ordinates codes ANISN and DOT as well as the 3-dimensional Monte Carlo code MORSE. The data sets from which DLC-23 are derived are listed in ref.3.
The library contains data for H, Be, 10-B, C, N, O, Na, Mg, Al, Si, K, Ca, Ti, Cr, Mn, Fe, Ni, Cu, Mo, Ta, W, Pb, 235-U, 238-U, 239-Pu, and 240-Pu.
top ]
4. METHOD OF SOLUTION

The source for the neutron cross sections was primarily the ENDF/B-2 library, although some data were taken from other sources, when necessary, as indicated in ref.3.
The SUPERTOG code was used to generate resonance corrected fine group cross sections for 104 energy groups from ENDF/B library.
Single-level Breit-Wigner or multi-level Breit-Wigner resonance parameters were used by SUPERTOG to generate point cross sections for the resonance nuclides. Approximately 100 points per resolved resonance were used to integrate the point cross sections for the fine groups. In the unresolved resonance region 81 points per fine group were used for the integration. A 1/E spectral weighting function was used.
The multigroup neutron cross sections in a 22 energy group structure were obtained from the 104 group cross sections by averaging the various elemental cross sections across a fine group flux calculated by ANISN for a uranium-water mixture using fine group cross sections. This weighting function is given in ref.3.
The secondary gamma-ray production cross sections were calculated for an 18 group gamma energy structure by the MUG code. The multigroup neutron cross sections, the secondary gamma production cross sections, and the gamma-ray transport cross sections were coupled to form a 40 group set. This is the same 40 group structure as used by Straker for various shielding calculations and it is tabulated in ref.3.
Calculations of the neutron and gamma-ray fluence from several shielding problems have been performed and some results of these calculations are discussed in ref.2.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
top ]
6. TYPICAL RUNNING TIME

To read the CASK data from a card image tape and rewrite it on an unformatted tape requires 23 seconds on the IBM 360/91.
ZZ-CASK/F (DLC-0023/03): The library generator test case was executed by NEA-DB on IBM 370/168 in less than 5 CPU seconds.
top ]
7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
top ]
8. RELATED AND AUXILIARY PROGRAMS

LIBGEN - is a modified version of the library generation routine which is available in the ANISN code  package. This version will read data from a card image tape, the mode by which CASK is distributed and write an unformatted tape for  direct use with ANISN.
top ]
9. STATUS
Package ID Status date Status
DLC-0023/03 27-APR-1983 Tested at NEADB
top ]
10. REFERENCES

- G.W. Morrison, E.A. Straker, and R.H. Odegaarden:
  'A Coupled Neutron and Gamma-Ray Multigroup Cross Section Library for Use in Shielding Calculations'
  Trans. Am. Nuc. Soc., 15, 535 (1972).
- G.W. Morrison, E.A. Straker, and R.H. Odegaarden:
  'The Use of the MORSE Monte Carlo Code to Solve Shielding and Criticality Problems of Spent Fuel Casks'
  Trans. Am. Nucl. Soc., 15, 547 (1972).
- R.W. Roussin and J.B. Wright:
  'Contents, Energy Group Structure, and Weighting Function Used for DLC-23/Cask'
  Informal Notes (1972).
DLC-0023/03, included references:
- CASK-81 - 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections
  for Shipping Cask Analysis. ORNL DLC-23 Updated (June 16, 1981).
top ]
11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0023/03 FORTRAN-IV
top ]
13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
top ]
14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  The current version DLC-23D is dated March 1974.
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

NAME AND ESTABLISHMENT OF AUTHOR.
     Neutron Physics and Mathematics Divisions, ORNL
     Science Applications, Inc. Huntsville, Alabama, U. S. A.
     Div. of Material Licensing, U.S.A.E.C., Washington, D.C.
top ]
16. MATERIAL AVAILABLE
DLC-0023/03
File name File description Records
DLC0023_03.003 ZZ-DLC-23E/CASK INFORMATION FILE 45
DLC0023_03.004 DATA LIBRARY FOR ALL MATERIALS 6735
DLC0023_03.005 AUXILIARY PROGRAM SOURCE 140
DLC0023_03.006 JCL TO RUN AUXILIARY PROGRAM 11
DLC0023_03.007 INPUT FOR TEST CASE 1
DLC0023_03.008 DATA LIBRARY FOR ZR 268
DLC0023_03.009 OUTPUT OF TEST CASE 4
top ]
17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: containers, cross sections, data, gamma radiation, multigroup, neutrons, shielding.