Surface-pseudosource method for calculating the antisymmetric single-group neutron distribution in a cylindrical reactor cell

Journal Article · Sat Feb 01 00:00:00 EST 1986 · Sov. At. Energy (Engl. Transl.); (United States)

OSTI ID:5593473

Boyarinov, V F

A method of calculating the antisymmetric neutron distributions in the single group approximation is proposed. A multizone cylindrical cell is considered and the neutron distribution in zone h of the cell is described by the single-group neutron-transfer equation in the transport approximation. The authors discuss using the surfacpseudosource method to calculate the distributions and the matrixfactorizing method is described. The ORAR-Ts program is examined which calculates the single-group antisymmetric neutron distributions in a cylindrical reactor cell with a specified current at the external cell boundary in the G/sub 1/ and G/sub 3/ approximations of the SPM. Calculation results are presented.

• OSTI ID: 5593473
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Vol. 59:2
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
NEUTRONS
ONE-GROUP THEORY
REACTOR CORES
NEUTRON TRANSPORT
REACTOR LATTICES
BOUNDARY CONDITIONS
COMPUTERIZED SIMULATION
COORDINATES
EXECUTIVE CODES
FACTORIZATION
GREEN FUNCTION
MATRIX ELEMENTS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
O CODES
REACTOR KINETICS
SPHERICAL HARMONICS METHOD
V CODES
BARYONS
COMPUTER CODES
DIFFERENTIAL EQUATIONS
ELEMENTARY PARTICLES
EQUATIONS
FERMIONS
FUNCTIONS
HADRONS
KINETICS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEONS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR COMPONENTS
SIMULATION
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter