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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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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.
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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.
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.
SUPREM - edits and converts MACKLIB data to form suitable for input to ANISN or DTF-4.
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).
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 |
Keywords: ENDF/B, cross sections, data, thermonuclear reactions.