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Computer Science Division, Union Carbide Corporation (United States); Neutron Physics Division, Oak Ridge National Laboratory Oak Ridge, Tennessee (United States); Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)1975
AbstractAbstract
[en] 1 - 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. 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. 2 - 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
Primary Subject
Source
1 Oct 1975; [html]; Available on-line: http://www.nea.fr/abs/html/dlc-0027.html; Country of input: International Atomic Energy Agency (IAEA); 2 refs.
Record Type
Miscellaneous
Literature Type
Software; Numerical Data
Country of publication
ALUMINIUM, CALCIUM, CARBON, COMPUTER PROGRAM DOCUMENTATION, EVALUATED DATA, GAMMA RADIATION, GROUP CONSTANTS, HYDROGEN, IRON, MEV RANGE, MULTIGROUP THEORY, NEUTRON FLUX, NEUTRONS, NITROGEN, NUCLEAR DATA COLLECTIONS, OXYGEN, PARTICLE PRODUCTION, POTASSIUM, SILICON, SODIUM, WEBSITES, WEIGHTING FUNCTIONS, Z CODES
ALKALI METALS, ALKALINE EARTH METALS, BARYONS, COMPUTER CODES, CROSS SECTIONS, DATA, DOCUMENT TYPES, ELECTROMAGNETIC RADIATION, ELEMENTARY PARTICLES, ELEMENTS, ENERGY RANGE, FERMIONS, FUNCTIONS, HADRONS, INFORMATION, IONIZING RADIATIONS, METALS, NEUTRON TRANSPORT THEORY, NONMETALS, NUCLEONS, NUMERICAL DATA, RADIATION FLUX, RADIATIONS, SEMIMETALS, TRANSITION ELEMENTS, TRANSPORT THEORY
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