DLC-0060 ZZ-MACKLIB-4. (Abstract last modified 25-JUL-1983)
1.
NAME OR DESIGNATION OF PROGRAM - ZZ-MACKLIB-4. 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-0060/04 IBM 3081 IBM 3081
3.
DESCRIPTION OF PROBLEM OR FUNCTION - 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. 5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - 6.
TYPICAL RUNNING TIME - 7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - SUPREM - edits and converts MACKLIB data to form suitable for input to ANISN or DTF-4. 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED - 14.
ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - The current version of the library is dated August 1974. 15.
NAME AND ESTABLISHMENT OF AUTHOR - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: CROSS SECTIONS, DATA, ENDF/B, THERMONUCLEAR REACTIONS
Program-name Package-ID Status
ZZ-MACKLIB-4 DLC-0060/01 Obsolete
ZZ-MACKLIB-4 DLC-0060/02 Obsolete
ZZ-MACKLIB-4 DLC-0060/03 Obsolete
ZZ-MACKLIB-4 DLC-0060/04 Tested
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
DLC-0060/04:
RIPOFF Converts data optionally into FIDO input format
or ANISN binary format.
DLC-0060/01: 25-JUL-1983 Obsolete
DLC-0060/02: 25-JUL-1983 Obsolete
DLC-0060/03: 25-JUL-1983 Obsolete
DLC-0060/04: 25-JUL-1983 Tested at NEADB
- 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:
- 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)_
DLC-0060/04: FORTRAN+ASSEMBLER
Nuclear Engineering Department
University of Wisconsin
Madison, Wisconsin 53706, U. S. A.
and
Radiation Shielding Information Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
DLC-0060/04:
DLC0060_04.001 ZZ-MACKLIB-4 INFORMATION FILE 65 records
DLC0060_04.002 71N/36G-GRP KERMA LIB (ACTIVITY TABLE FMT) 30466 records
DLC0060_04.003 71N/36G-GRP KERMA LIB (ALTERNATE FMT) 24028 records
DLC0060_04.004 71N/36G-GRP GAMMA PRODUCTION DATA 21286 records
DLC0060_04.005 RETRIEVAL PROGRAM SOURCE (FORTRAN-4) 729 records
DLC0060_04.006 RETRIEVAL PROGRAM JCL & DATA 35 records
DLC0060_04.007 RETRIEVAL PROGRAM OUTPUT 465 records
DLC0060_04.008 RIPOF SOURCE (FORTRAN-4) 417 records
DLC0060_04.009 RIPOF ADDITIONAL ROUTINES (FORTRAN-4) 718 records
DLC0060_04.010 RIPOF ADDITIONAL ROUTINES (ASSEMBLER) 73 records
DLC0060_04.011 RIPOF JCL & DATA FOR TEST CASE 46 records
DLC0060_04.012 RIPOF OUTPUT OF TEST CASE 877 records
DLC0060_04.013 RETRIEVAL PROGRAM (CDC VERSION) 989 records
DLC0060_04.014 RIPOF ALTERNATE SOURCE (FORTRAN-4) 432 records
- J. Gamma Heating and Shield Design
- X. Magnetic Fusion Research
- Z. Data.
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