Intercomparison of the finite difference and nodal discrete ordinates and surface flux transport methods for a LWR pool-reactor benchmark problem in X-Y geometry

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6635480

O'Dell, R D; Stepanek, J; Wagner, M R

The aim of the present work is to compare and discuss the three of the most advanced two dimensional transport methods, the finite difference and nodal discrete ordinates and surface flux method, incorporated into the transport codes TWODANT, TWOTRAN-NODAL, MULTIMEDIUM and SURCU. For intercomparison the eigenvalue and the neutron flux distribution are calculated using these codes in the LWR pool reactor benchmark problem. Additionally the results are compared with some results obtained by French collision probability transport codes MARSYAS and TRIDENT. Because the transport solution of this benchmark problem is close to its diffusion solution some results obtained by the finite element diffusion code FINELM and the finite difference diffusion code DIFF-2D are included.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Swiss Federal Inst. for Reactor Research, Wuerenlingen; Kraftwerk Union A.G., Erlangen (Germany, F.R.)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6635480
• Report Number(s): LA-UR-83-29; CONF-830304-14; ON: DE83006051
• Resource Relation: Conference: American Nuclear Society topical conference on computational methods, Salt Lake City, UT, USA, 28 Mar 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR KINETICS
DISCRETE ORDINATE METHOD
FINITE DIFFERENCE METHOD
NEUTRON TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS
COMPUTER CALCULATIONS
MATHEMATICAL MODELS
NEUTRON FLUX
ITERATIVE METHODS
KINETICS
NUMERICAL SOLUTION
RADIATION FLUX
REACTORS
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation