DLC-0028 ZZ-DLC-28.
ZZ DLC-28, 73-Group Neutron and Gamma Coupled Cross-Section for CTR Transport Calculation
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-DLC-28 | DLC-0028/01 | Tested | 01-OCT-1975 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| DLC-0028/01 | IBM 370 series | IBM 370 series |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
FORMAT: ANISN, DOT, or MORSE.
NUMBER OF GROUPS: 52 neutron groups plus 21 gamma-ray groups.
NUCLIDES: materials typically considered for use in some conceptual fusion reactor neutronics studies.These materials include Li-6, Li-7, Nb, C, Fe, Cu, Li, Al-203, Mg, H, O, Pb, Ta, V, and B.
ORIGIN: ENDF/B or DNA data sets; for lead and boron, the GAM-2 library at ORNL.
WEIGHTING SPECTRUM: The data were collapsed from a fine-group structure using a weighting function typical of the average spectrum in a fusion reactor blanket.
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The DLC-28 library can be used for neutron and secondary gamma-ray transport or for primary gamma-ray transport in fusion reactor neutronics studies.
DLC-28/CTR is a coupled set of cross sections for materials typically considered for use in some conceptual fusion reactor neutronics studies. These materials include 6-Li, 7-Li, Nb, C, Fe, Cu, Li, Al-203, Mg, H, O, Pb, Ta, V, and B.
FORMAT: ANISN, DOT, or MORSE.
NUMBER OF GROUPS: 52 neutron groups plus 21 gamma-ray groups.
NUCLIDES: materials typically considered for use in some conceptual fusion reactor neutronics studies.These materials include Li-6, Li-7, Nb, C, Fe, Cu, Li, Al-203, Mg, H, O, Pb, Ta, V, and B.
ORIGIN: ENDF/B or DNA data sets; for lead and boron, the GAM-2 library at ORNL.
WEIGHTING SPECTRUM: The data were collapsed from a fine-group structure using a weighting function typical of the average spectrum in a fusion reactor blanket.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The DLC-28 library can be used for neutron and secondary gamma-ray transport or for primary gamma-ray transport in fusion reactor neutronics studies.
DLC-28/CTR is a coupled set of cross sections for materials typically considered for use in some conceptual fusion reactor neutronics studies. These materials include 6-Li, 7-Li, Nb, C, Fe, Cu, Li, Al-203, Mg, H, O, Pb, Ta, V, and B.
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4. METHOD OF SOLUTION
The data were collapsed from a fine-group structure using a weighting function typical of the average spectrum in a fusion reactor blanket.
With the exception of lead and boron, 100 energy-group neutron cross sections were obtained from ENDF/B or DNA data sets using SUPERTOG. A flux weighting function of 1/E was used in SUPERTOG and all resonance nuclides were treated as infinitely dilute. The energy group structure coincided with the GAM-2 group structure for the top 99 groups, and the 100th group was a thermal group (Maxwellian distribution was assumed).
For lead and boron, the GAM-2 library at ORNL was employed to obtain the 100-group neutron cross sections.
SMUG, an updated version of MUG, was used to calculate 21 energy-group gamma-ray transport cross sections for all nuclides except lead and boron. The gamma-ray transport cross sections for lead and boron are from MUG.
Secondary gamma-ray production cross sections for 100 neutron groups and 21 gamma-ray groups were obtained from several data bases.
A coupled 100 neutron energy-group and 21 gamma-ray energy- group cross section set was formed and then collapsed to 52 neutron groups plus 21 gamma-ray groups using the group collapsing feature of the ANISN code. The spectrum used for the collapsing was, therefore, a spatial average of the energy distribution in a fusion reactor blanket.
The energy-group structures used are given in ref. 1. a P3 Legendre expansion was used to represent neutron elastic scattering and photon Compton scattering.
The data were collapsed from a fine-group structure using a weighting function typical of the average spectrum in a fusion reactor blanket.
With the exception of lead and boron, 100 energy-group neutron cross sections were obtained from ENDF/B or DNA data sets using SUPERTOG. A flux weighting function of 1/E was used in SUPERTOG and all resonance nuclides were treated as infinitely dilute. The energy group structure coincided with the GAM-2 group structure for the top 99 groups, and the 100th group was a thermal group (Maxwellian distribution was assumed).
For lead and boron, the GAM-2 library at ORNL was employed to obtain the 100-group neutron cross sections.
SMUG, an updated version of MUG, was used to calculate 21 energy-group gamma-ray transport cross sections for all nuclides except lead and boron. The gamma-ray transport cross sections for lead and boron are from MUG.
Secondary gamma-ray production cross sections for 100 neutron groups and 21 gamma-ray groups were obtained from several data bases.
A coupled 100 neutron energy-group and 21 gamma-ray energy- group cross section set was formed and then collapsed to 52 neutron groups plus 21 gamma-ray groups using the group collapsing feature of the ANISN code. The spectrum used for the collapsing was, therefore, a spatial average of the energy distribution in a fusion reactor blanket.
The energy-group structures used are given in ref. 1. a P3 Legendre expansion was used to represent neutron elastic scattering and photon Compton scattering.
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DLC-0028/01
| File name | File description | Records |
|---|---|---|
| DLC0028_01.001 | DATA LIBRARY (BCD) | 14521 |
| DLC0028_01.002 | RETRIEVAL PROGRAM (F4) | 140 |
| DLC0028_01.003 | JCL + DATA FOR SAMPLE PROBLEM | 8 |
Keywords: ENDF/B, cross sections, data, fusion reactions, gamma radiation, multigroup, neutrons, transport theory.