R-function solution of the neutron transport equation

Conference · Sat Dec 31 23:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5199558

Altiparmakov, D V

In developing new methods for numerical solution of the neutron transport equation, two main objectives are (a) to reduce the number of unknowns and (b) to increase the flexibility in geometric description. Most current methods satisfy only one of these objectives at best. For instance, finite elements provide an effective means of treating complex geometry, however, a fine spatial mesh is usually required to achieve the needed accuracy. On the other hand, the number of unknowns is significantly reduced by the nodal methods that must deal with rectangular geometry. The R-function theory offers great possibilities to meet both objectives, as it has been already shown in neuron diffusion calculations. The intention of this paper is to point out certain potentials of the R-function method applied to neutron transport calculations. For that purpose the even-parity equation is solved in a square lattice cell with a cylindrical fuel element.

• OSTI ID: 5199558
• Report Number(s): CONF-890604--
• Journal Information: Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 59; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACCURACY
C CODES
COMPUTER CALCULATIONS
COMPUTER CODES
CONVERGENCE
F CODES
FUEL ELEMENTS
GEOMETRY
MATHEMATICS
MESH GENERATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
PHYSICS
REACTOR COMPONENTS
REACTOR LATTICES
REACTOR PHYSICS
SPACE DEPENDENCE
TRANSPORT THEORY