Verification of a neutronic code for transient analysis in reactors with Hex-z geometry

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22105601

Gonzalez-Pintor, S.; Verdu, G. ^[1]; Ginestar, D. ^[2]

---

1. Departamento de Ingenieria Quimica Y Nuclear, Universitat Politecnica de Valencia, Cami de Vera, 14, 46022. Valencia (Spain)
2. Departamento de Matematica Aplicada, Universitat Politecnica de Valencia, Cami de Vera, 14, 46022. Valencia (Spain)

Due to the geometry of the fuel bundles, to simulate reactors such as VVER reactors it is necessary to develop methods that can deal with hexagonal prisms as basic elements of the spatial discretization. The main features of a code based on a high order finite element method for the spatial discretization of the neutron diffusion equation and an implicit difference method for the time discretization of this equation are presented and the performance of the code is tested solving the first exercise of the AER transient benchmark. The obtained results are compared with the reference results of the benchmark and with the results provided by PARCS code. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105601
• Resource Relation: Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 11 refs.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICAL METHODS AND COMPUTING
BENCHMARKS
COMPUTER CODES
FINITE ELEMENT METHOD
FUEL ELEMENT CLUSTERS
GEOMETRY
NEUTRON DIFFUSION EQUATION
TRANSIENTS
WWER TYPE REACTORS