Published October 2002 | Version v1
Miscellaneous

Three-dimensional whole core transport calculation method and performance of the DeCART code

  • 1. KAERI, Taejon (Korea, Republic of)

Description

The three-dimensional (3D) transport calculation method implemented in a whole core neutron transport code DeCART is presented and its performance is examined in terms of solution accuracy and execution speed. The 3D flux calculation in DeCART is based on a transverse-integration method in which the radial and axial dependencies are handled separately. The radial dependence is resolved by the elaborated two-dimensional method of characteristics (MOC) whereas the axial dependence is dealt with the simple one-dimensional diffusion model. The global balance of the 3D flux distribution is incorporated by the coarse mesh finite difference (CMFD) formulation. It is shown that the CMFD formulation enables the approximate three-dimensional transport calculation through the transverse-integration, and furthermore it is very effective in achieving rapid convergence. The accuracy of the approximate 3D whole-core transport calculation method is proved by analyzing rodded variations of the C5G7 MOX heterogeneous core benchmark problem for which Monte Carlo solutions are generated as the reference

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[10 p.]

Conference

Title
2002 autumn meeting of the KNS
Dates
24-25 Oct 2002
Place
Yongpyoung (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34063438
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
D CODES; FINITE DIFFERENCE METHOD; MONTE CARLO METHOD; NEUTRON TRANSPORT; PERFORMANCE; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR COMPONENTS

Optional Information

Notes
9 refs, 4 figs, 4 tabs