last modified: 25-JUL-1983 | catalog | categories | new | search |

DLC-0060 ZZ-MACKLIB-4.

ZZ MACKLIB-4, 171-Neutron, 36-Gamma Group Response Function Library from ENDF/B-IV

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-MACKLIB-4.
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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-MACKLIB-4 DLC-0060/04 Tested 25-JUL-1983

Machines used:

Package ID Orig. computer Test computer
DLC-0060/04 IBM 3081 IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION

  FORMAT: MACK Activity Tables, ANISN and DTF-4

  NUMBER OF GROUPS: 171 neutron groups and 36 gamma groups.

NUCLIDES: H, He, Li-6, Li-7, Be, B-10, B-11, C, N, O, F, Na, Mg Al, Si, Cl, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Nb, Mo, Ta, W-182  W-183, W-184, W-186, Pb, Th-232, Pa, U-233, U-234, U-235, U-236 U-238, Np, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241 and Am-243.

ORIGIN: ENDF/B-IV
WEIGHTING SPECTRUM: same as that used for the library ZZ-VITAMIN-C.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
MACKLIB-IV is a library of nuclear response functions (activities) for 49 materials of interest in fusion and fusion-fission hybrid systems. It employs the CTR energy group structure of 171 neutron groups and 36 gamma groups. Included in the library are neutron and gamma KERMA factors, gas production and tritium breeding functions, and all important reaction cross sections. The following materials are included: H, He, 6Li, 7Li, Be, 10B, 11B, C, N, O, F, Na, Mg, Al, Si, Cl, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Nb, Mo, Ta, 182W, 183W, 184W, 186W, Pb, 232Th, Pa, 233U, 234U, 235U, 236U, 238U, Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am and 243Am.
The library is distributed in card image FIDO format; the array structure can be read directly into the transport code ANISN in order to calculate reaction rates.
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4. METHOD OF SOLUTION

The library was prepared from ENDF/B-IV data using the program MACK-IV. It employs the CTR energy group structure of 171 neutron groups and 36 gamma groups. The new version of the data library was generated using the same weight function as that used for the library ZZ-VITAMIN-C. The library is available in the new format of the "MACK Activity Tables" and in an alternate structured format.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

SUPREM - edits and converts MACKLIB  data to form suitable for input to ANISN or DTF-4.
DLC-0060/04
RIPOFF              Converts data optionally into FIDO input format
                    or ANISN binary format.
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9. STATUS
Package ID Status date Status
DLC-0060/04 25-JUL-1983 Tested at NEADB
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10. REFERENCES

- M.A. Abdou and R.W. Roussin

  'MACKLIB, 100-Group Neutron Fluence-to-Kerma Factors and Reaction Cross Sections Generated by the MACK Computer Program from Data in ENDF Format'
  ORNL-TM-3995.
- M.A. Abdou, C.W. Maynard, and R.Q. Wright

  'MACK, A Computer Program to Calculate Neutron Energy Release
  Parameters (Fluence-to-Kerma Factors) and Multigroup Neutron Reaction Cross Sections from Nuclear Data in ENDF Format'
  ORNL-TM-3994 (July 1973).
- J.J. Ritts, M. Solomito, and D. Steiner

  'Kerma Factors and Secondary Gamma-Ray Sources for Some Elements of Interest in Thermonuclear Blanket Assemblies'
  ORNL-TM-2564 (June 1970).
DLC-0060/04, included references:
- Y. Gohar and M.A. Abdou:
  MACKLIB-IV, A Library of Nuclear Response Functions Generated with
  the MACK-iv Computer Program from ENDFB-IV.
  ANL/FPP/TM-106  (March 1978)_
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0060/04 FORTRAN+ASSEMBLER
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  The current version of the library is dated August 1974.
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Argonne National Laboratory, Argonne, Illinois, USA
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16. MATERIAL AVAILABLE
DLC-0060/04
File name File description Records
DLC0060_04.001 ZZ-MACKLIB-4 INFORMATION FILE 65
DLC0060_04.002 71N/36G-GRP KERMA LIB (ACTIVITY TABLE FMT) 30466
DLC0060_04.003 71N/36G-GRP KERMA LIB (ALTERNATE FMT) 24028
DLC0060_04.004 71N/36G-GRP GAMMA PRODUCTION DATA 21286
DLC0060_04.005 RETRIEVAL PROGRAM SOURCE (FORTRAN-4) 729
DLC0060_04.006 RETRIEVAL PROGRAM JCL & DATA 35
DLC0060_04.007 RETRIEVAL PROGRAM OUTPUT 465
DLC0060_04.008 RIPOF SOURCE (FORTRAN-4) 417
DLC0060_04.009 RIPOF ADDITIONAL ROUTINES (FORTRAN-4) 718
DLC0060_04.010 RIPOF ADDITIONAL ROUTINES (ASSEMBLER) 73
DLC0060_04.011 RIPOF JCL & DATA FOR TEST CASE 46
DLC0060_04.012 RIPOF OUTPUT OF TEST CASE 877
DLC0060_04.013 RETRIEVAL PROGRAM (CDC VERSION) 989
DLC0060_04.014 RIPOF ALTERNATE SOURCE (FORTRAN-4) 432
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: ENDF/B, cross sections, data, thermonuclear reactions.