APOLLO: a general code for transport, slowing-down and thermalization calculations in heterogeneous media
From national topical meeting on mathematical models and computational techniques for analysis of nuclear systems; Ann Arbor, Michigan, USA (8 Apr 1973). In mathematical models and computational techniques for analysis of nuclear systems. APOLLO calculates the space-and-energy-dependent flux for a one dimensional medium, in the multigroup approximation of the transport equation. For a one dimensional medium, refined collision probabilities have been developed for the resolution of the integral form of the transport equation; these collision probabilities increase accuracy and save computing time. The interaction between a few cells can also be treated by the multicell option of APOLLO. The diffusion coefficient and the material buckling can be computed in the various B and P approximations with a linearly anisotropic scattering law, even in the thermal range of the spectrum. Eventually this coefficient is corrected for streaming by use of Benoist's theory. The self-shielding of the heavy isotopes is treated by a new and accurate technique which preserves the reaction rates of the fundamental fine structure flux. APOLLO can perform a depletion calculation for one cell, a group of cells or a complete reactor. The results of an APOLLO calculation are the space-and-energy-dependent flux, the material buckling or any reaction rate; these results can also be macroscopic cross sections used as input data for a 2D or 3D depletion and diffusion code in reactor geometry. 10 references. (auth)
- Research Organization:
- Centre d'Etudes Nucleaires, Saclay, France; American Nuclear Society. Michigan Section
- NSA Number:
- NSA-29-007172
- OSTI ID:
- 4392112
- Report Number(s):
- CONF-730414-P1
- Resource Relation:
- Conference: National topical meeting on mathematical models and computational techniques for analysis of nuclear systems, Ann Arbor, Michigan, USA, 8 Apr 1973; Other Information: Orig. Receipt Date: 30-JUN-74; Related Information: Mathematical models and computational techniques for analysis of nuclear systems
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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