Numerical solution of conservation equations in the transient model for the system thermal - hydraulics in the Korsar computer code
- 1. Alexandrov Research Institute of Technology, NITI, Sosnovy bor, Leningrad region (Russian Federation)
Description
The functional part of the KORSAR computer code is based on the computational unit for the reactor system thermal-hydraulics and other thermal power systems with water cooling. The two-phase flow dynamics of the thermal-hydraulic network is modelled by KORSAR in one-dimensional two-fluid (non-equilibrium and nonhomogeneous) approximation with the same pressure of both phases. Each phase is characterized by parameters averaged over the channel sections, and described by the conservation equations for mass, energy and momentum. The KORSAR computer code relies upon a novel approach to mathematical modelling of two-phase dispersed-annular flows. This approach allows a two-fluid model to differentiate the effects of the liquid film and droplets in the gas core on the flow characteristics. A semi-implicit numerical scheme has been chosen for deriving discrete analogs the conservation equations in KORSAR. In the semi-implicit numerical scheme, solution of finite-difference equations is reduced to the problem of determining the pressure field at a new time level. For the one-channel case, the pressure field is found from the solution of a system of linear algebraic equations by using the tri-diagonal matrix method. In the branched network calculation, the matrix of coefficients in the equations describing the pressure field is no longer tri-diagonal but has a sparseness structure. In this case, the system of linear equations for the pressure field can be solved with any of the known classical methods. Such an approach is implemented in the existing best-estimate thermal-hydraulic computer codes (TRAC, RELAP5, etc.) For the KORSAR computer code, we have developed a new non-iterative method for calculating the pressure field in the network of any topology. This method is based on the tri-diagonal matrix method and performs well when solving the thermal-hydraulic network problems. (author)
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Additional details
Publishing Information
- Imprint Pagination
- [2 p.]
- Report number
- INIS-FR--1012
Conference
- Title
- 9. international conference on nuclear engineering
- Dates
- 8-12 Apr 2001
- Place
- Nice, Acropolis (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 33020096
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DROPLETS; HYDRAULICS; K CODES; NUMERICAL SOLUTION; REACTORS; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; FLUID FLOW; FLUID MECHANICS; MECHANICS; PARTICLES