Basis for Coupled 3-D Neutronics-Thermal-Hydraulics

Aragonés Beltrán, José María (2008). Basis for Coupled 3-D Neutronics-Thermal-Hydraulics. In: "Seminar on the Transfer of Knowledge Gained through CSNI Activities in the Field of Thermal-hydraulics, THICKET-2008", 05/05/2008-09/05/2008, Pisa,Italia.

Description

Title: Basis for Coupled 3-D Neutronics-Thermal-Hydraulics
Author/s:
  • Aragonés Beltrán, José María
Item Type: Presentation at Congress or Conference (Article)
Event Title: Seminar on the Transfer of Knowledge Gained through CSNI Activities in the Field of Thermal-hydraulics, THICKET-2008
Event Dates: 05/05/2008-09/05/2008
Event Location: Pisa,Italia
Title of Book: Proceedings of THICKET-2008: Seminar on the Transfer of Knowledge Gained through CSNI Activities in the Field of Thermal-hydraulics
Date: 2008
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

The purpose of this seminar is first to discuss the basis of the coupling between 3-D Neutron- Kinetics and Thermal-Hydraulics codes, including the control and 3-D variables to interchange, the transform of the 3-D NK and TH core nodalizations, and the schemes for temporal coupling and time-step control. As representative examples of the NK-TH core coupling, we discuss first the integration of a 3-D NK nodal code with a TH subchannel code, for detailed transient core analysis; and second the coupling of 3-D NK nodal codes with TH system codes, for general transient and safety analysis. In chapter 2, we analyze several prototype model transients in PWR, where large 3-D core asymmetries are found and the NK-TH coupling is quite significant, including loss-of-flow and symmetric and asymmetric core cooling, considering the effects on the responses of the excore detectors. In chapter 3, we discuss the analysis of an increase-of-flow transient actually occurred in an operating PWR and the comparison with the measured data. In chapter 4, we summarize the phenomena and results of the calculations of the NEA/NSC Benchmark on the main steam line break (MSLB) transient in a PWR. Finally, we will discuss the state-of-the-art issues in LWR coupled NK-TH 3-D transient analysis and ongoing and planned computational developments.

More information

Item ID: 4707
DC Identifier: http://oa.upm.es/4707/
OAI Identifier: oai:oa.upm.es:4707
Official URL: http://www.nea.fr/nsd/workshops/thicket-2008/programme.html
Deposited by: Memoria Investigacion
Deposited on: 04 Nov 2010 12:22
Last Modified: 20 Apr 2016 13:49
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