last modified: 01-OCT-1975 | catalog | categories | new | search |

DLC-0029 ZZ-MACKLIB.

ZZ MACKLIB, Nuclear Response Function Library for CTR and Hybrid Fission Fusion System Materials

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-MACKLIB.
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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 DLC-0029/01 Tested 01-OCT-1975

Machines used:

Package ID Orig. computer Test computer
DLC-0029/01 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION


%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

  FORMAT: GAM structure

  NUMBER OF GROUPS: 100 neutron.

NUCLIDES: V, W, Cu, He, Li, H, Cr, Ni, Ta, O, Al, Pb, Be, B, Na, Nb, C, Fe.

  ORIGIN: ENDF/B-III
                            A                      5  (E-Eo)**2
  WEIGHTING SPECTRUM:W(E) = - + B ( dT f(T) exp (- -  --------- ))
                            E                      4   Eo KT

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The computer code MACK was used to produce averaged neutron reaction cross sections and KERMA factors in the 100-group GAM structure. Data are included for materials commonly used in CTR neutronics studies. 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.  A simple retrieval program is included which can be used to edit the library, mix cross sections or collapse the group structure. The output is either in FIDO format, or in binary ANISN library tape format.
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4. METHODS

METHOD OF SOLUTION. The basic evaluated cross section data from which the resulting group averaged values were derived was ENDF/B-3. The weighting spectrum used in the energy averaging accounts for the energy distribution of d-t neutrons. The effect of radioactive decay was included for reaction product nuclei with half-lives less than 50 days.
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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 OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

MACKLIB-IV is a significant upgrade of the earlier version MACKLIB (2).
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9. STATUS
Package ID Status date Status
DLC-0029/01 01-OCT-1975 Tested at NEADB
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10. REFERENCES

- Y. Gohar, M.A. Abdou:
  MACKLIB-IV. A Library of Nuclear Response Functions Generated
  with the MACK-IV Computer Program from ENDF/B-IV.
  ANL/FPP/TM-106 (March 1978)
- M.A. Abdou, Y. Gohar, R.Q. Wright:
  MACK-IV, A New Version of MACK: A Program to Calculate Nuclear
  Response Functions from Data in ENDF/B Format.
  ANL/FPP/TM-75-5 (1978)
DLC-0029/01, included references:
- M.A. Abdou, R.W. Roussin:
  MACKLIB. Neutron Fluence-to-Kerma Factor Library Generated with
  MACK from Nuclear Data in ENDF Format.
  ORNL-TM-3995 (August 1974).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0029/01 FORTRAN-IV
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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 AUTHOR

Y. Gohar
Fusion Power Program
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439, U.S.A.

M.A. Abdou
School of Nuclear Engineering
Georgia Institute of Technology
Atlanta, Georgia 30332, U.S.a.
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16. MATERIAL AVAILABLE
DLC-0029/01
File name File description Records
DLC0029_01.001 DATA LIBRARY (BCD) 5995
DLC0029_01.002 RETRIEVAL PROGRAM (F4) 611
DLC0029_01.003 JCL + DATA FOR SAMPLE PROBLEM 8
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: breeding, cross sections, data, fission reactors, fusion reactors, gamma radiation, group constants, kerma factors, multigroup, neutrons, response functions, tritium.