A new coarse-mesh method for transient core calculations of LWRs
- Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- Hanyang Univ., Seoul (Korea, Republic of)
The core design and safe operation in light water reactors (LWRs) require fast and accurate determination of the neutron characteristics for steady-state and transient core calculations. In recent years, there were many attempts to solve transient problems using various nodal methods [e.g., analytic nodal method (ANM), nodal expansion method (NEM)] to get accurate solutions. These methods also reduce the execution time, compared with the traditional finite difference method, without sacrificing accuracy. However, one of the main difficulties associated with nodal methods is the determination of spatial coupling coefficients. Until recently, this problem has seriously limited the practical use of nodal methods. In this study, we introduce correction factors (called discontinuity factors) for each node to provide a relationship between the node-averaged flux and the surface-averaged flux and currents in transient core calculations.
- OSTI ID:
- 6671685
- Report Number(s):
- CONF-921102--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 66; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ANALYTIC FUNCTIONS
BWR TYPE REACTORS
CALCULATION METHODS
DESIGN
ENRICHED URANIUM REACTORS
FINITE DIFFERENCE METHOD
FUNCTIONS
ITERATIVE METHODS
NEUTRON FLUX
NODAL EXPANSION METHOD
NUMERICAL SOLUTION
POWER REACTORS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTORS
THERMAL REACTORS
TRANSIENTS
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS