Computer Programs
DLC-0027 ZZ-AMPX01.
ZZ AMPX01/27C, Coupled Neutron-Gamma Group Constant Library by AMPX for 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-AMPX01 | DLC-0027/01 | Tested | 01-NOV-1979 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| DLC-0027/01 | IBM 370 series | IBM 370 series |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
FORMAT: ANISN, DOT, MORSE
NUMBER OF GROUPS: The neutron energy range (15 MeV to thermal) is described by 104 groups. The gamma-ray energy range (10 MeV to 0.02 MeV) is described by 22 energy groups.
NUCLIDES: N, O, Al, H, K, Si, Ca, Na, C, and Fe.
ORIGIN: For all materials, except C and K, was the Defense Nuclear Agency Working Cross Section Library dated September 1972. The K and C data came from ENDF/B-3.
WEIGHTING SPECTRUM: For the neutrons 1/E in the fast range and Maxwellian (300 deg.K) in the thermal range. For the gamma-ray interaction a flat weighting function was used.
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The DLC-27 library was generated for use in albedo studies of neutrons incident on various types of concrete. It is probably also suitable for neutrons, gamma-rays, or coupled neutron and secondary gamma-ray transport through concrete-like materials.It is a coupled set of neutron and gamma-ray cross sections for the elements N, O, Al, H, K, Si, Ca, Na, C, and Fe.
FORMAT: ANISN, DOT, MORSE
NUMBER OF GROUPS: The neutron energy range (15 MeV to thermal) is described by 104 groups. The gamma-ray energy range (10 MeV to 0.02 MeV) is described by 22 energy groups.
NUCLIDES: N, O, Al, H, K, Si, Ca, Na, C, and Fe.
ORIGIN: For all materials, except C and K, was the Defense Nuclear Agency Working Cross Section Library dated September 1972. The K and C data came from ENDF/B-3.
WEIGHTING SPECTRUM: For the neutrons 1/E in the fast range and Maxwellian (300 deg.K) in the thermal range. For the gamma-ray interaction a flat weighting function was used.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The DLC-27 library was generated for use in albedo studies of neutrons incident on various types of concrete. It is probably also suitable for neutrons, gamma-rays, or coupled neutron and secondary gamma-ray transport through concrete-like materials.It is a coupled set of neutron and gamma-ray cross sections for the elements N, O, Al, H, K, Si, Ca, Na, C, and Fe.
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4. METHOD OF SOLUTION
The AMPX system was utilized to generate the entire coupled library in a single computer run. For all materials except C and K, the basic evaluated data from which the multigroup library was derived was the Defense Nuclear Agency Working Cross Section Library dated September 1972. The K data came from ENDF/B-3. The C was ENDF/B-3 with photon production added to describe a single inelastically and isotropically produced gamma-ray. The neutron energy range (15 MeV to thermal) is described by 104 groups having the same energy structure as used for DLC-9. The gamma-ray energy range (10 MeV to 0.02 MeV) is described by 22 energy groups. For generating the multigroup neutron interaction and gamma-ray production cross sections, the assumption was made that the neutron flux variation (weighting function) was 1/E in the fast range and Maxwellian (300 deg.K) in the thermal range. For the gamma-ray interaction multigroup cross section generation, a flat weighting function was used. The neutron and gamma-ray scattering processes are represented by a P5 Legendre expansion.
The AMPX system was utilized to generate the entire coupled library in a single computer run. For all materials except C and K, the basic evaluated data from which the multigroup library was derived was the Defense Nuclear Agency Working Cross Section Library dated September 1972. The K data came from ENDF/B-3. The C was ENDF/B-3 with photon production added to describe a single inelastically and isotropically produced gamma-ray. The neutron energy range (15 MeV to thermal) is described by 104 groups having the same energy structure as used for DLC-9. The gamma-ray energy range (10 MeV to 0.02 MeV) is described by 22 energy groups. For generating the multigroup neutron interaction and gamma-ray production cross sections, the assumption was made that the neutron flux variation (weighting function) was 1/E in the fast range and Maxwellian (300 deg.K) in the thermal range. For the gamma-ray interaction multigroup cross section generation, a flat weighting function was used. The neutron and gamma-ray scattering processes are represented by a P5 Legendre expansion.
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DLC-0027/01
| File name | File description | Records |
|---|---|---|
| DLC0027_01.001 | INFORMATION | 5 |
| DLC0027_01.002 | SOURCE (F4,EBCDIC) | 143 |
| DLC0027_01.003 | LIBRARY | 17032 |
| DLC0027_01.004 | JCL | 61 |
| DLC0027_01.005 | SAMPLE PROBLEM INPUT | 1 |
| DLC0027_01.006 | SAMPLE PROBLEM OUTPUT | 60 |
Keywords: ENDF/B, concretes, cross sections, data, gamma radiation, multigroup, neutrons, shielding, transport theory.