Development and validation of the three-dimensional dynamic code - KIKO3D - 217
Creators
- 1. KFKI Atomic Energy Research Institute, H-1525 Budapest 114, POB 49 (Hungary)
Description
A three-dimensional reactor dynamics program - KIKO3D - for coupled neutron kinetics and thermohydraulics calculation of VVER type pressurized water reactor cores has been developed and benchmarked. For solution of the time dependent neutronic equations, a nodal method has been elaborated which is general concerning the geometry, the symmetries of the nodes, and the concrete form of the neutronic equations to be solved inside the nodes (transport or diffusion equation). Only the linear anisotropy of neutron flux on the node boundaries is utilised. Generalized response matrices for the time dependent problem are introduced which can be derived also from the response matrix of the stationary problem. The obtained time dependent matrix equations show similar structure to the not discretized equations. Therefore, the Improved Quasi Static factorization of the time dependent matrix equations can be carried out in the usual way leading to the point kinetic and the shape function equations. In the KIKO3D code, the above general nodal method was applied for the special case of rectangular and hexagonal homogenized nodes in which the diffusion equation is to be solved. In this special case, the traditional response matrices of the stationary problem and the generalized matrices necessary for the time dependent problem can be given by analytical formulas. The accuracy of the introduced approximations have been validated against rectangular and hexagonal benchmark problems. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 25 p.
Conference
- Title
- ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium
- Acronym
- Physor 2000
- Dates
- 7-12 May 2000
- Place
- Pittsburgh, PA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54119226
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANISOTROPY; BENCHMARKS; DIFFUSION EQUATIONS; FACTORIZATION; GEOMETRY; MATRICES; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRONS; REACTOR CORES; REACTOR KINETICS; SYMMETRY; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; TRANSPORT; WWER TYPE REACTORS
- Descriptors DEC
- BARYONS; DIFFERENTIAL EQUATIONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; FLUID MECHANICS; HADRONS; HYDRAULICS; KINETICS; MATHEMATICS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 22 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)