Computer Programs

DLC-0029 ZZ-MACKLIB.

DLC-0029 ZZ-MACKLIB.

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

NAME, COMPUTER, PROBLEM, SOLUTION, AUXILIARIES, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM

ZZ-MACKLIB.

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2. COMPUTERS

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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

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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8. RELATED OR 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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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
DLC-0029/01	FORTRAN-IV

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15. NAME AND ESTABLISHMENT OF AUTHORS

Y. Gohar

Fusion Power Program

Argonne National Laboratory

9700 South Cass Avenue

Argonne, Illinois 60439, USA

M.A. Abdou

School of Nuclear Engineering

Georgia Institute of Technology

Atlanta, Georgia 30332, USA

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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

ZZZ. ARCHIVE

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