Improvement of neutron kinetics module in TRAC-BF1code: one-dimensional nodal collocation method
Creators
- 1. Universidade Politecnica de Valencia (UPV), Valencia (Spain)
- 2. SEA Propulsion S.L., Madrid (Spain)
- 3. Iberdrola Ingenieria y Construcion S.A.U., Madrid (Spain)
Description
The TRAC-BF1 one-dimensional kinetic model is a formulation of the neutron diffusion equation in the two energy groups' approximation, based on the analytical nodal method (ANM). The advantage compared with a zero-dimensional kinetic model is that the axial power profile may vary with time due to thermal-hydraulic parameter changes and/or actions of the control systems but at has the disadvantages that in unusual situations it fails to converge. The nodal collocation method developed for the neutron diffusion equation and applied to the kinetics resolution of TRAC-BF1 thermal-hydraulics, is an adaptation of the traditional collocation methods for the discretization of partial differential equations, based on the development of the solution as a linear combination of analytical functions. It has chosen to use a nodal collocation method based on a development of Legendre polynomials of neutron fluxes in each cell. The qualification is carried out by the analysis of the turbine trip transient from the NEA benchmark in Peach Bottom NPP using both the original 1D kinetics implemented in TRAC-BF1 and the 1D nodal collocation method. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- INIS-BR--14631
Conference
- Title
- international nuclear atlantic conference
- Acronym
- INAC 2013
- Dates
- 24-29 Nov 2013
- Place
- Recife, PE (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 45110552
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FINITE DIFFERENCE METHOD; KINETICS; LEGENDRE POLYNOMIALS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NODAL EXPANSION METHOD; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; VOID FRACTION
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID MECHANICS; FUNCTIONS; HYDRAULICS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; POLYNOMIALS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 4 figs., 1 tab.