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
·
OSTI ID:6635480
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 Lab., NM (USA); 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
- Country of Publication:
- United States
- Language:
- English
Similar Records
A variational synthesis nodal discrete ordinates method
Data visualization for ONEDANT and TWODANT discrete ordinates codes
Benchmarking with high-order nodal diffusion methods
Journal Article
·
Tue Jun 01 00:00:00 EDT 1999
· Nuclear Science and Engineering
·
OSTI ID:357694
Data visualization for ONEDANT and TWODANT discrete ordinates codes
Conference
·
Thu Dec 30 23:00:00 EST 1993
·
OSTI ID:10114369
Benchmarking with high-order nodal diffusion methods
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7122302
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CALCULATIONS
DISCRETE ORDINATE METHOD
FINITE DIFFERENCE METHOD
ITERATIVE METHODS
KINETICS
MATHEMATICAL MODELS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
RADIATION FLUX
REACTOR KINETICS
REACTORS
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CALCULATIONS
DISCRETE ORDINATE METHOD
FINITE DIFFERENCE METHOD
ITERATIVE METHODS
KINETICS
MATHEMATICAL MODELS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
RADIATION FLUX
REACTOR KINETICS
REACTORS
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS