Show simple item record

dc.contributor.authorPérez-Ferragut, Marina
dc.contributor.authorFreixa Terradas, Jordi
dc.contributor.authorMas de les Valls Ortiz, Elisabet
dc.contributor.otherUniversitat Politècnica de Catalunya. Departament de Física
dc.date.accessioned2017-03-22T12:32:06Z
dc.date.issued2015
dc.identifier.citationPérez-Ferragut, M., Freixa, J., Mas de les Valls, E. RELAP/SCDAPSIM/MOD4.0 modification for transient accident scenario of test blanket modules involving helium flows into heavy liquid metal. A: International Topical Meeting on Nuclear Reactor Thermal Hydraulics. "Proceedings of 16th International Topical Meeting on Nuclear Thermal Hydraulics (NURETH'16): Chicago, Illinois: August 30-September 4th, 2015". Chicago, Illinois: 2015, p. 6030-6043.
dc.identifier.isbn978-151081184-3
dc.identifier.urihttp://hdl.handle.net/2117/102796
dc.description.abstractThe Institute for Plasma Research (IPR), India, is currently involved in the design and development of its Test Blanket Module (TBM) for testing in ITER (International Thermo nuclear Experimental Reactor). The Indian TBM concept is a Lead-Lithium cooled Ceramic Breeder (LLCB), which utilizes lead-lithium eutectic alloy (LLE) as tritium breeder, neutron multiplier and coolant. The first wall facing the plasma is cooled by helium gas. Thermal hydraulic safety analyses are being carried out with the system code RELAP/SCDAPSIM/MOD4.0 whic h was initially designed to predict the behaviour of light water reactor systems during normal and accident conditions. The code is being developed as part of the international SCDAP Development and Training Pr ogram (SDTP) coordinated by Innovative Systems Software (ISS). The modeling strategy of the RELAP code for the simulation of two-phase flows is based on a single-fluid two-phase approach with a set of momentum, energy and mass equations for each phase. The two phases are liquid-water and gas phase mixture of steam and non-condensable gases. Phase interactions, such as interphase friction and heat transfer, are modelled by closure relations based on experimental/numerical correlations that depend on the flow regime. In cooperation with ISS, the IPR team has implemented LLE liquid phase thermodynamic properties as a working fluid alternative to water and appropriate wall-to-LLE heat transfer correlations. However, in order to analyze some of the postulated off-normal events, there is a need to simulate the mixing of helium and Lead-Lithium fluids In the standard RELAP/SCDAPSIM/MOD4.0 ve rsion it is not possible to simulate a mixture of a non-water fluid with a non-condensable. In addition to that, t he available flow regime maps for vertical and horizontal flows in RELAP are specific for steam/water pair, which may not be suitable for LLE/helium pair. The Technical University of Catalonia is cooperating with IPR to adapt the RELAP/SCDAPSIM/MOD4.0 code to allow the si mulation of LLE and he mixture. This paper presents the results of the first step of the project, which includes a state of the art on simulation of liquid metals mixed with non-condensable using system codes, the implementation of the necessary code modifications to allow for a LLE/he mixture a nd preliminary results using the modified code version for horizontal and vertical configurations.
dc.format.extent14 p.
dc.language.isoeng
dc.rightsAttribution-NonCommercial-NoDerivs 3.0 Spain
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/es/
dc.subjectÀrees temàtiques de la UPC::Energies
dc.subjectÀrees temàtiques de la UPC::Energies::Energia nuclear
dc.subject.lcshLiquid metals
dc.subject.lcshNuclear fusion
dc.subject.otherLiquid metal
dc.subject.otherNon-condensable gas
dc.subject.otherSystem codes
dc.subject.otherFusion technology
dc.titleRELAP/SCDAPSIM/MOD4.0 modification for transient accident scenario of test blanket modules involving helium flows into heavy liquid metal
dc.typeConference lecture
dc.subject.lemacMetalls líquids
dc.subject.lemacFusió nuclear
dc.contributor.groupUniversitat Politècnica de Catalunya. ANT - Advanced Nuclear Technologies Research Group
dc.contributor.groupUniversitat Politècnica de Catalunya. GREENTECH - Grup de Recerca en Tecnologies Renovables
dc.rights.accessRestricted access - publisher's policy
local.identifier.drac19744643
dc.description.versionPostprint (published version)
dc.date.lift10000-01-01
local.citation.authorPerez, M.; Freixa, J.; Mas de les Valls, E.
local.citation.contributorInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics
local.citation.pubplaceChicago, Illinois
local.citation.publicationNameProceedings of 16th International Topical Meeting on Nuclear Thermal Hydraulics (NURETH'16): Chicago, Illinois: August 30-September 4th, 2015
local.citation.startingPage6030
local.citation.endingPage6043


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record