DLC-0029 ZZ-MACKLIB.
ZZ MACKLIB, Nuclear Response Function Library for CTR and Hybrid Fission Fusion System Materials
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
[ top ]
[ top ]
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 |
[ top ]
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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
[ top ]
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.
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.
[ top ]
[ top ]
[ top ]
[ top ]
[ top ]
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)
- 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).
[ top ]
[ top ]
[ top ]
[ top ]
[ top ]
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 |
Keywords: breeding, cross sections, data, fission reactors, fusion reactors, gamma radiation, group constants, kerma factors, multigroup, neutrons, response functions, tritium.