Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry

Lozano Montero, Juan Andrés and Jiménez Escalante, Javier and García Herranz, Nuria and Aragonés Beltrán, José María (2009). Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry. In: "International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009)", May 3-7, 2009, Saratoga Springs, New York. ISBN 978-0-89448-069-0. pp. 1-13.

Description

Title: Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry
Author/s:
  • Lozano Montero, Juan Andrés
  • Jiménez Escalante, Javier
  • García Herranz, Nuria
  • Aragonés Beltrán, José María
Item Type: Presentation at Congress or Conference (Article)
Event Title: International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009)
Event Dates: May 3-7, 2009
Event Location: Saratoga Springs, New York
Title of Book: International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009)
Date: 2009
ISBN: 978-0-89448-069-0
Subjects:
Freetext Keywords: ANDES, neutronic-thermalhydraulics coupling, hexagonal geometry, coarse mesh scale.
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Nuclear [hasta 2014]
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

In this paper, the extension of the nodal diffusion code ANDES, based on the ACMFD method, to hexagonal geometry is presented, as well as its coupling with the thermal-hydraulic (TH) code COBRA-IIIc/MIT-2 for such hexagonal problems. In extending the ACMFD method to hexagonal assemblies, triangular-Z nodes are used, taking advantage of the mesh refinement capabilities implicit within that geometry. The existing TH coupling for Cartesian geometry applications has also been extended to hexagonal problems, with the capability to model the core using either assembly wise channels (hexagonal mesh) or a higher refinement with six channels per fuel assembly (triangular mesh). Achieving this level of TH mesh refinement with COBRA-IIIc code provides a better estimation of the in-core 3D flow distribution. Therefore, the work presented here introduces an improvement in the TH VVER core modelling, where in the best case scenario, just twenty axial layers and one channel per fuel assembly were used. As a result, the neutronic and thermal-hydraulics (N-TH) coupled code, ANDES/COBRA-IIIc, extensively verified in Cartesian geometry cores analysis, can also be applied to full threedimensional VVER core problems. Some verification results are provided, corresponding to 2nd exercises (HZP and HP steady states) of the OECD/NEA- VVER-1000 Coolant Transient benchmark and to the HZP and HFP steady states of the V1000CT2-EXT2 NURESIM benchmark.

Funding Projects

TypeCodeAcronymLeaderTitle
Unspecified516560 (FI6O)NURESIMUnspecified6th EURATOM Framework Programme, within the RTD Integrated Project NURESIM “European Platform for Nuclear Reactor Simulations”

More information

Item ID: 44367
DC Identifier: http://oa.upm.es/44367/
OAI Identifier: oai:oa.upm.es:44367
Official URL: http://www.ans.org/store/item-700346-CD/
Deposited by: Memoria Investigacion
Deposited on: 11 Jan 2017 17:42
Last Modified: 12 Jan 2017 16:52
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