DLC-0029 ZZ-MACKLIB. (Abstract last modified 01-OCT-1975)
1.
NAME OR DESIGNATION OF PROGRAM - ZZ-MACKLIB. 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
DLC-0029/01 IBM 370 series IBM 370 series
3.
DESCRIPTION OF PROBLEM OR FUNCTION - 4.
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.
5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - 6.
TYPICAL RUNNING TIME - 7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - MACKLIB-IV is a significant upgrade of the earlier version MACKLIB (2).
9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHOR - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: BREEDING, CROSS SECTIONS, DATA, FISSION REACTORS, FUSION REACTORS, GAMMA RADIATION, GROUP CONSTANTS, KERMA FACTORS, MULTIGROUP, NEUTRONS, RESPONSE FUNCTIONS, TRITIUM
Program-name Package-ID Status
ZZ-MACKLIB DLC-0029/01 Tested
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
DLC-0029/01: 01-OCT-1975 Tested at NEADB
- 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:
- 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).
DLC-0029/01: FORTRAN-IV
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.
DLC-0029/01:
DLC0029_01.001 DATA LIBRARY (BCD) 5995 records
DLC0029_01.002 RETRIEVAL PROGRAM (F4) 611 records
DLC0029_01.003 JCL + DATA FOR SAMPLE PROBLEM 8 records
- J. Gamma Heating and Shield Design
- X. Magnetic Fusion Research
- Z. Data.
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