Discrete ordinates methods for radiation transport

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6435082

Badruzzaman, A; Fan, W C ^[1]

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1. Sandia National Lab., Albuquerque, NM (USA)

The discrete ordinates (S{sub N}) method, first developed for stellar atmospheres, has been used extensively on various other radiation transport problems. In reactor analysis the method is generally used to generate parameters for design models based on more approximate but less expensive methods (such as diffusion theory) so that the spatial-spectrum coupling is represented accurately on a microscopic reaction rate level. It has a decisive advantage over Monte Carlo methods in computing the pin and assembly power profiles. In shielding problems where the penetration of the radiation can be deep, the method is used widely in design calculations. In oil-well logging problems, which also involve deep penetration and have a stringent accuracy requirement on the detector responses, the method complements the Monte Carlo techniques. One early application of the S{sub N} method was on one-dimensional radiative transfer problems. The discrete ordinates method has also been used in charged-particle transport problems. While the method has been applied primarily to static problems, one-dimensional time-dependent codes have existed since the early 1970s. In this paper the authors briefly review the basic method, illustrate its applications, discuss its merits and pitfalls, and enumerate the recent advances in the attendant numerical techniques that have enhanced the capabilities of the method.

• OSTI ID: 6435082
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACCURACY
BENCHMARKS
BOLTZMANN EQUATION
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
DIFFERENTIAL EQUATIONS
DISCRETE ORDINATE METHOD
EIGENVALUES
EQUATIONS
FINITE DIFFERENCE METHOD
GROUP THEORY
ITERATIVE METHODS
KINETICS
MATHEMATICS
MESH GENERATION
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
NUMERICAL SOLUTION
PARTIAL DIFFERENTIAL EQUATIONS
RADIATION TRANSPORT
REACTOR KINETICS
REACTORS
SHIELDING
SPACE DEPENDENCE
THREE-DIMENSIONAL CALCULATIONS
TIME DEPENDENCE
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS