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AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M6 cladding
Jeremy Bischoff,Christine Delafoy,Christine Vauglin,Pierre Barberis,Cedric Roubeyrie,Delphine Perche,Dominique Duthoo,Frederic Schuster,Jean-Christophe Brachet,Elmar W. Schweitzer,Kiran Nimishakavi 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.2
AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced accident-tolerant fuelscladding concepts ranging from near-term evolutionary (Cr-coated zirconium alloy cladding) to longtermrevolutionary (SiC/SiC composite cladding) solutions, relying on its worldwide teams and partnerships,with programs and irradiations planned both in Europe and the United States. The most advanced and mature solution is a dense, adherent chromium coating on zirconium alloycladding, which was initially developed along with the CEA and EDF in the French joint nuclear R&Dprogram. The evaluation of the out-of-pile behavior of the Cr-coated cladding showed excellent results,suggesting enhanced reliability, enhanced operational flexibility, and improved economics in normaloperating conditions. For example, because chromium is harder than zirconium, the Cr coating providesthe cladding with a significantly improved wear resistance. Furthermore, Cr-coated samples exhibitextremely low corrosion kinetics in autoclave and prevents accelerated corrosion in harsh environmentssuch as in water with 70 ppm Li leading to improved operational flexibility. Finally, AREVA NP has fabricated a physical vapor deposition prototype machine to coat full-lengthcladding tubes. This machine will be used for the manufacturing of full-length lead test rods in commercialreactors by 2019.
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Isabelle Gu enot-Delahaie,Jerome Sercombe,Thomas Helfer,Patrick Goldbronn,Eric Federici,Thomas Le Jolu,Aurore Parrot,Christine Delafoy,Christian Bernaudat 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.2
The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NPwithin the PLEIADES software environment models the behavior of fuel rods during irradiation incommercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidentalconditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the lattercase of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod bytaking account of mechanisms in a way that models the physics as closely as possible, encompassing allpossible stages of the transient as well as various fuel/cladding material types and irradiation conditionsof interest. On the way to complying with these objectives, ALCYONE development and validation shallinclude tests on PWR-UO2 fuel rods with advanced claddings such as M5® under “low pressureelowtemperature” or “high pressureehigh temperature” water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses onrecent developments dedicated on the one hand to nonsteady water heat and mass transport and on theother hand to the modeling of grain boundary cracking-induced fission gas release and swelling. Thisarticle then compares some simulations of RIA transients performed on UO2-M5® fuel rods in flowingsodium or stagnant water coolant conditions to the relevant experimental results gained from testsperformed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It showsin particular to what extent ALCYONEdstarting from base irradiation conditions it itself computesdiscurrently able to handle both the first stage of the transient, namely the pellet-cladding mechanicalinteraction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to beperformed under prototypical PWR conditions within the CABRI International Program. M5® is a trademark or a registered trademark of AREVA NP in the USA or other countries.
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