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High Temperature Material Processes: An International Quarterly of High-Technology Plasma Processes

Publicou 4 edições por ano

ISSN Imprimir: 1093-3611

ISSN On-line: 1940-4360

The Impact Factor measures the average number of citations received in a particular year by papers published in the journal during the two preceding years. 2017 Journal Citation Reports (Clarivate Analytics, 2018) IF: 0.4 The Immediacy Index is the average number of times an article is cited in the year it is published. The journal Immediacy Index indicates how quickly articles in a journal are cited. Immediacy Index: 0.1 The Eigenfactor score, developed by Jevin West and Carl Bergstrom at the University of Washington, is a rating of the total importance of a scientific journal. Journals are rated according to the number of incoming citations, with citations from highly ranked journals weighted to make a larger contribution to the eigenfactor than those from poorly ranked journals. Eigenfactor: 0.00005 The Journal Citation Indicator (JCI) is a single measurement of the field-normalized citation impact of journals in the Web of Science Core Collection across disciplines. The key words here are that the metric is normalized and cross-disciplinary. JCI: 0.07 SJR: 0.198 SNIP: 0.48 CiteScore™:: 1.1 H-Index: 20

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PLASMA TRANSFERRED ARC ROTARY FURNACE FOR "CORIUM" MELTING

Volume 1, Edição 3, 1997, pp. 409-420
DOI: 10.1615/HighTempMatProc.v1.i3.100
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RESUMO

In the event of a highly unlikely core melt-down accident in Pressurised Water Nuclear Reactors (PWRs), scenarios in which the reactor pressure vessel fails and the core melt mixture (called corium and mainly composed of UO2, ZrO2, Zr, Fe and fission products) relocates into the reactor cavity, cannot be excluded. In this context, large R&D efforts within the European Union are currently directed towards ex-vessel corium behaviour with particular emphasis on long-term corium retention and coolability in order to keep it in the containment.
In France, the Nuclear Reactor Division (CEA/DRN), with the support of its industrial partners : EDF and FRAMATOME, has undertaken an experimental programme, named VULCANO (for « Versatile UO2 Lab for Corium Analyses and Observation »). The objective of this programme is to study corium behaviour under representative conditions with the view to qualifying the future EPR (European Pressurised Reactor) core catcher concept based on spreading the corium on a large surface and subsequently cooling by flooding with water. The main aim of this programme is to improve understanding of the phenomena which play a key role in the physico-chemical and thermal-hydraulic behaviour of corium, especially spreading and interaction with structure materials in particular sacrificial concrete and refractory protective layer.
The VULCANO facility mainly consists of a furnace and a test section whose geometry depends on the specific objectives of each experiment. The furnace has been designed to accommodate about one hundred kilograms of corium up to 3000 K composed of representative materials : depleted UO2, ZrO2, Zr and Fe.
The technique chosen to melt the corium constitutive materials is to heat, in a rotary plasma arc furnace, the load composed of a mixture of powders up to 3000 K. Thanks to the rotation of the furnace, powders are centrifugated allowing the formation on the furnace axis of a 300 kW plasma arc at very high temperature (10000 to 20000K depending on gases) which first heats and melts load surface layer by thermal radiation; then, deeper layers by conduction. The furnace is cooled by water circulation in a double jacket.
Seven thermocouples embedded in powder load measure temperature evolution inside the furnace during all the melting process; the signals are transmitted through an infrared telemetry device which rotates with the furnace. A bichromatic pyrometer measuring melt surface temperature at the furnace outlet gives hot temperature. These measurements enable us to control the process and to decide on the time at which the molten product can be poured into the test section.
The melting process is modelled by using the CASTEM 2000 finite elements computing code in order to reach three goals : improvement of the melting process, preparation of experiments and helping control monitoring.

CITADO POR
  1. Journeau Christophe, Piluso Pascal, Haquet Jean-François, Boccaccio Eric, Saldo Valérie, Bonnet Jean-Michel, Malaval Sophie, Carénini Laure, Brissonneau Laurent, Two-dimensional interaction of oxidic corium with concretes: The VULCANO VB test series, Annals of Nuclear Energy, 36, 10, 2009. Crossref

  2. Journeau Christophe, Boccaccio Eric, Brayer Claude, Cognet Gérard, Haquet Jean-François, Jégou Claude, Piluso Pascal, Monerris José, Ex-vessel corium spreading: results from the VULCANO spreading tests, Nuclear Engineering and Design, 223, 1, 2003. Crossref

  3. Piluso Pascal, Trillon Gilbert, Journeau Christophe, The UO2–ZrO2 system at high temperature (T>2000K): importance of the meta-stable phases under severe accident conditions, Journal of Nuclear Materials, 344, 1-3, 2005. Crossref

  4. Sevón Tuomo, Journeau Christophe, Ferry Lionel, VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete, Annals of Nuclear Energy, 59, 2013. Crossref

  5. Journeau Christophe, Haquet Jean-Francois, Spindler Bertrand, Spengler Claus, Foit Jerzy, The VULCANO VE-U7 Corium spreading benchmark, Progress in Nuclear Energy, 48, 3, 2006. Crossref

  6. Journeau Christophe, Bonnet Jean Michel, Boccaccio Eric, Piluso Pascal, Monerris Jose, Breton Michel, Fritz Gerald, Sevón Tuomo, Pankakoski Pekka H., Holmström Stefan, Virta Jouko, European Experiments on 2-D Molten Core Concrete Interaction: HECLA and VULCANO, Nuclear Technology, 170, 1, 2010. Crossref

  7. Journeau Christophe, de Pascale Claire, Brayer Claude, Cranga Michel, Convection in Transient Flows of Solidifying Oxidic Mixtures, in Interactive Dynamics of Convection and Solidification, 2001. Crossref

  8. Journeau C, Sudreau F, Magne S, Cognet G, Physico-chemical analyses and solidification path reconstruction of multi-component oxidic spread melts, Materials Science and Engineering: A, 299, 1-2, 2001. Crossref

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