Pierre Guillermier
Areva
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Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1 | 2008
Virginie Basini; Sander de Groot; Pierre Guillermier; François Charollais; Frédéric Michel; David Bottomley; Jean-Pol Hiernaut; Michael A. Fütterer; Karl Verfondern; T J Abram; Martin Kissane
Within the scope of the 5th EURATOM Framework Programme (FP) for the HTR-F and HTR-F1 projects, a new 4-year integrated project on very high temperature reactors (RAPHAEL: ReActor for Process Heat And Electricity) was started in April 2006 as part of the 6th Framework Programme. The Sub-Project on Fuel Technology (SP-FT) is one of eight sub-projects constituting the RAPHAEL project. R&D conducted in this sub-project focuses on understanding fuel behaviour, determining the limits of state-of-the-art fuel, and developing potential performance improvements. Fabrication processes were worked out for alternative fuel kernel composition (UCO instead of UO2 ) and coating (ZrC instead of SiC): i) UCO microstructure reduces fission product migration and is thus considered superior to UO2 under high burn-ups and high temperature gradients. For this reason, the manufacturing feasibility of UCO kernels using modified external sol-gel routes was addressed. The calcining and sintering steps were particularly studied. ii) For its better high temperature performance, ZrC is a candidate coating material for replacing SiC in TRISO (TRistructural ISOtropic) particles. One of the objectives was therefore to deposit a stoichiometric ZrC layer without impurities. An “analytical irradiation” experiment currently performed in the HFR — named PYCASSO for PYrocarbon irradiation for Creep And Swelling/Shrinkage of Objects — was set up to measure the changes in coating material properties as a function of neutron fluence, with samples coming from the new fabrication process. This experiment was started in April 2008 and will provide data on particle component behaviour under irradiation. This data is required to upgrade material models implemented in the ATLAS fuel simulation code. The PYCASSO irradiation experiment is a true Generation IV VHTR effort, with Korean and Japanese samples included in the irradiation. Further RAPHAEL results will be made available to the GIF VHTR Fuel and Fuel Cycle project partners in the future. Post-irradiation examinations and heat-up tests performed on fuel irradiated in an earlier project are being performed to investigate the behaviour of state-of-the-art fuel in VHTR normal and accident conditions. Very interesting results from destructive examinations performed on the HFR-EU1bis pebbles were obtained, showing a clear temperature (and high burn-up) influence on both kernel changes (including fission product behaviour) and the coating layers. Based on fuel particle models established earlier, the fuel modelling capabilities could be further improved: i) Modelling of fuel elements containing thousands of particles is expected to enable a statistical approach to mechanical particle behaviour and fission product release. ii) A database on historical and new fuel properties was built to enable validation of models. This paper reports on recent progress and main results of the RAPHAEL sub-project on fuel technology.Copyright
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1 | 2008
Julien Banchet; David Tisseur; Pierre Guillermier
The HTR TRISO particle consists of a fissile kernel and surrounding layers, whose density and thickness are among the key fuel parameters. Destructive methods i.e. the sink float method and image analysis of ceramography, were developed in the past and are still used to evaluate these particle parameters. Although exhibiting great accuracy, these methods generate effluents and wastes, and are extremely cost/time consuming. In the framework of the AREVA NP HTR R&D program, the development of nondestructive evaluation methods as alternatives to destructive methods is carried out and aims at a new HTR Fuel QC strategy. In this scope, an innovative method was developed to automatically measure particle layer density and thickness from X-Ray Phase Contrast Imaging (PCI). First tested at the European Synchroton Radiation Facility (ESRF), this method was then applied to a custom built industrial demonstrator. Comparisons between the density and thickness values obtained by the developed method and their corresponding values obtained with destructive methods justify progressing to the validation phase. Particle samples were selected among the particle batches that were characterized by destructive methods. Layer density and thickness were determined by the X-Ray based technique on the industrial demonstrator as well as at the ESRF. Correlation levels obtained from this benchmark demonstrated that both parameters can be confidently measured by the developed method. Additionally, it is important to stress that this technique provides the opportunity to directly determine buffer density on finite particles as opposed to the sink float method. Thanks to its accuracy, its rapidity and its absence of waste generation, it is planned to implement the X-Ray thickness and density measurement method on the French lab scale fuel line. It was also decided to enter the characterization work package of the IAEA Coordinated Research Project 6 in order to benchmark the AREVA NP method with foreign techniques and materials.Copyright
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2 | 2008
Sander de Groot; Virginie Basini; Pierre Guillermier; Klaas Bakker; Kazuhiro Sawa; Young-Woo Lee; Jean-Michel Escleine; Marc Perez; Shohei Ueta; Bong-Goo Kim
Within the Raphael (V)HTR 6th framework EU-program, the PYCASSO experiments have been devised to investigate coating behaviour under irradiation. Samples have been included from CEA (France), JAEA (Japan) and KAERI (Republic of Korea), which makes this irradiation a real Generation IV effort. The experiment is a separate effect test, where the influence of fuel (coating corrosion or micro structural change due to fission products), thermal gradients, and variation in coating microstructure and dimensions have been minimized by the use of dummy kernels (Al2O3 and ZrO2), high conductivity particle holder material combined with low energy production of the kernels, and strict (fabrication) quality control and selection procedures respectively. The purpose of the experiment is threefold for the partners involved: - for CEA to determine the behaviour of pyrocarbon under irradiation, especially the interaction of pyrocarbon swelling and creep with SiC coating layers. The results will be used to validate and improve HTR fuel performance modelling. - for JAEA to investigate the behaviour of ZrC coatings, which have been successfully manufactured, but require post-irradiation investigation and characterization. - for KAERI to determine the influence of fabrication of pyrocarbon layers with different densities on the behaviour under irradiation. The paper will go into more detail on the goals to be achieved by the different partners. The PYCASSO-I irradiation is performed in the High Flux Reactor (HFR) in Petten, The Netherlands. The experiment accommodates temperature regions of 900, 1000 and 1100°C, and contains 76 separate particle sample holders. The PYCASSO-I irradiation is a completely new design and will be described in detail, including the route from the concept definition via feasibility studies, fabrication and assembly, up to the irradiation, which took only 1, 5 year. At the time of the conference, the PYCASSO-I irradiation will be finished and a full evaluation of the irradiation will be presented. Additionally, the future post irradiation examination planned for the PYCASSO-I samples and the details of the PYCASSO-II irradiation will be outlined.Copyright
Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2 | 2008
Pierre Guillermier; Julien Banchet; David Tisseur; Sébastien Hermosilla Lara; Marc Bivert; Marc Piriou
In order to ensure HTR fuel qualification, as well as reactor safety, particles need to satisfy a set of specifications including particle integrity. To achieve this goal, AREVA NP has been engaged for several years in a R&D program aiming at the development of innovative industrial non destructive evaluation methods for HTR fuel as alternatives to destructive methods. After investigating a number of potential techniques, development has been focused on vision and eddy currents, both aiming at crack detection. High resolution Phase Contrast X-Ray imaging was also studied for structural defects characterization. For all these techniques, besides the development of HTR fuel dedicated control methods, equipment and probes were specifically designed, tested and optimized thanks to experiments conducted on real and artificial flaws, yielding for some of the methods to potential industrialization and quality control performed over 100% of the fuel production.Copyright
Nuclear Engineering and Design | 2010
Sander de Groot; Pierre Guillermier; Kazuhiro Sawa; Jean-Michel Escleine; Shohei Ueta; Virginie Basini; Klaas Bakker; Young-Woo Lee; Marc Perez; Bong-Goo Kim
Archive | 1996
Pierre Guillermier; Christophe Texier; Manuel Organista
Archive | 1995
Pierre Guillermier; Alain Blocquel
Archive | 1999
Pierre Guillermier; Alain Blocquel
Archive | 1997
Pierre Guillermier; Christophe Texier; Manuel Organista
Archive | 1994
Pierre Guillermier; Alain Blocquel