Multigroup calculation of antisymmetric neutron distributions in a cylindrical cell

Journal Article · Fri May 01 00:00:00 EDT 1987 · Sov. At. Energy (Engl. Transl.); (United States)

OSTI ID:5254264

Boyarinov, V F

The authors construct a model for the neutron distribution in a multizone cylindrical reactor lattice with coaxial zones using the neutron diffusion equation and multigroup theory. The operator-splitting method is used to separate the spatial and energy variables and the surface-pseudosource method is used to solve the spatial aspects of the problem.

• OSTI ID: 5254264
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Vol. 61:5; Other Information: Translated from At. Ehnerg.; 61: No. 5, 324-329(Nov 1986)
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR LATTICES
MULTIGROUP THEORY
BOUNDARY CONDITIONS
COMPUTERIZED SIMULATION
CYLINDRICAL CONFIGURATION
ENERGY SPECTRA
FISSION NEUTRONS
FLUX DENSITY
MATHEMATICAL OPERATORS
MATRICES
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON SOURCES
NEUTRON SPECTRA
NEUTRON TRANSPORT
SPATIAL DISTRIBUTION
VECTORS
BARYONS
CONFIGURATION
DIFFERENTIAL EQUATIONS
DISTRIBUTION
ELEMENTARY PARTICLES
EQUATIONS
FERMIONS
HADRONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEONS
PARTICLE SOURCES
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
SIMULATION
SPECTRA
TENSORS
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation