DLC-0018 ZZ-DLC-18/NAB.
ZZ DLC-18 NAB, 100 Neutron-Group Cross-Section Library of Na and Al for ANISN, DOT, MORSE Neutron Transport
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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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
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-DLC-18 | DLC-0018/01 | Tested | 01-APR-1974 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| DLC-0018/01 | Many Computers | Many Computers |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
FORMAT: ANISN, DOT, and MORSE
NUMBER OF GROUPS: 100 neutron group
NUCLIDES: sodium or sodium contained in aluminium tanks. With following impurities:
calcium 400 ppm
oxygen 200 ppm
potassium 150 ppm
hydrogen 50 ppm
ORIGIN: ENDF/B-3 MAT 1156 sodium and MAT 1135 aluminium.
WEIGHTING SPECTRUM: - 1/E weighting spectrum for non-thermal energies,
- thermal group cross sections were determined by assuming a Maxwellian weighting function and a constant scattering cross section and a 1/v absorption cross section.
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DLC-18 is suitable for multigroup neutron transport calculations in sodium or sodium contained in aluminium tanks, such as the ORNL-LMBNR sodium benchmark experiment (2). The retrieval program manipulates such that it can be used in codes such as ANISN, DOT, and MORSE.
FORMAT: ANISN, DOT, and MORSE
NUMBER OF GROUPS: 100 neutron group
NUCLIDES: sodium or sodium contained in aluminium tanks. With following impurities:
calcium 400 ppm
oxygen 200 ppm
potassium 150 ppm
hydrogen 50 ppm
ORIGIN: ENDF/B-3 MAT 1156 sodium and MAT 1135 aluminium.
WEIGHTING SPECTRUM: - 1/E weighting spectrum for non-thermal energies,
- thermal group cross sections were determined by assuming a Maxwellian weighting function and a constant scattering cross section and a 1/v absorption cross section.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
DLC-18 is suitable for multigroup neutron transport calculations in sodium or sodium contained in aluminium tanks, such as the ORNL-LMBNR sodium benchmark experiment (2). The retrieval program manipulates such that it can be used in codes such as ANISN, DOT, and MORSE.
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4. METHOD OF SOLUTION
The 100 neutron group, P3 data were produced by the ORNL Mathematics Division, using SUPERTOG, and a 1/E weighting spectrum for non-thermal energies. The energy group structure is that used for the GAM-2 which covers the energy range from 14.92 MeV to thermal. The thermal group cross sections were determined by assuming a Maxwellian weighting function and a constant scattering cross section and a 1/v absorption cross section.
This data represents a P3 Legendre expansion approximation for neutron elastic scattering. Inelastic neutron scattering was treated as isotropic in the lab system.
The multigroup cross sections were generated from a preliminary version of the ENDF/B-3 MAT 1156 sodium and MAT 1135 aluminium. Subsequent changes to the evaluated data prior to its official release as part of ENDF/B-3 would affect the data in DLC-18/NAB somewhat, but probably not significantly.
Because the materials used in the experiment were not free from impurities, these were included as follows
calcium 400 ppm
oxygen 200 ppm
potassium 150 ppm
hydrogen 50 ppm
The 100 neutron group, P3 data were produced by the ORNL Mathematics Division, using SUPERTOG, and a 1/E weighting spectrum for non-thermal energies. The energy group structure is that used for the GAM-2 which covers the energy range from 14.92 MeV to thermal. The thermal group cross sections were determined by assuming a Maxwellian weighting function and a constant scattering cross section and a 1/v absorption cross section.
This data represents a P3 Legendre expansion approximation for neutron elastic scattering. Inelastic neutron scattering was treated as isotropic in the lab system.
The multigroup cross sections were generated from a preliminary version of the ENDF/B-3 MAT 1156 sodium and MAT 1135 aluminium. Subsequent changes to the evaluated data prior to its official release as part of ENDF/B-3 would affect the data in DLC-18/NAB somewhat, but probably not significantly.
Because the materials used in the experiment were not free from impurities, these were included as follows
calcium 400 ppm
oxygen 200 ppm
potassium 150 ppm
hydrogen 50 ppm
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DLC-0018/01
| File name | File description | Records |
|---|---|---|
| DLC0018_01.001 | 100-GRP NEUTRON X-SEC LIBRARY FOR NA, AL | 4152 |
| DLC0018_01.002 | ANISN LIBRARY ROUTINE (SOURCE PROGRAM) | 140 |
| DLC0018_01.003 | ANISN LIBRARY ROUTINE SAMPLE PROBLEM DD-CARD | 4 |
| DLC0018_01.004 | ANISN LIBRARY ROUTINE SAMPLE PROBLEM OUTPUT | 8 |
Keywords: absorption, cross sections, data, elastic scattering, inelastic scattering, multigroup, neutrons, sodium.