Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code

Jiménez Escalante, Javier and Herrero Carrascosa, José Javier and Cuervo Gómez, Diana and Aragonés Beltrán, José María (2010). Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code. In: "17th Pacific Basin Nuclear Conference 2010, PBNC-2010", 24/10/2010 - 30/10/2010, Cancún, México.

Description

Title: Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code
Author/s:
  • Jiménez Escalante, Javier
  • Herrero Carrascosa, José Javier
  • Cuervo Gómez, Diana
  • Aragonés Beltrán, José María
Item Type: Presentation at Congress or Conference (Article)
Event Title: 17th Pacific Basin Nuclear Conference 2010, PBNC-2010
Event Dates: 24/10/2010 - 30/10/2010
Event Location: Cancún, México
Title of Book: Proceedings of the 17th Pacific Basin Nuclear Conference 2010, PBNC-2010
Date: 2010
Subjects:
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

Nowadays, coupled 3D neutron-kinetics and thermal-hydraulic core calculations are performed by applying a radial average channel approach using a meshing of one quarter of assembly in the best case. This approach does not take into account the subchannels effects due to the averaging of the physical fields and the loose of heterogeneity in the thermal-hydraulic modelization. Therefore the models do not have enough resolution to predict those subchannels effects which are important for the fuel design safety margins, because it is in the local scale, where we can search the hottest pellet or the maximum heat flux. The UPM advanced multi-scale neutron-kinetics and thermal-hydraulics methodologies being implemented in COBAYA3 include domain decomposition by alternate core dissections for the local 3D fine-mesh scale problems (pin cells/subchannels) and an analytical nodal diffusion solver for the coarse mesh scale coupled with the thermal-hydraulic using a modelization of one channel per assembly or per quarter of assembly. In this work, we address the domain decomposition by the alternate core dissections methodology applied to solve coupled 3D neutronic/thermal-hydraulic (N-TH) problems at the fine-mesh scale. The N-TH coupling at the cell-subchannel scale allows the treatment of the effects of the detailed TH feedbacks on cross-sections, thus resulting in better estimates of the local safety margins at the pin level.

More information

Item ID: 6884
DC Identifier: http://oa.upm.es/6884/
OAI Identifier: oai:oa.upm.es:6884
Official URL: http://www.pbnc2010.org.mx/
Deposited by: Memoria Investigacion
Deposited on: 18 May 2011 09:04
Last Modified: 20 Apr 2016 16:00
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