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" Pellet-clad Interaction in Water Reactor Fuels "
Organisation for Economic Co-operation and Development and Nuclear Energy Agency.
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BL
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672465
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b501654
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Organisation for Economic Co-operation and Development.
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Pellet-clad Interaction in Water Reactor Fuels : Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004 /\ Organisation for Economic Co-operation and Development and Nuclear Energy Agency.
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| Publication Statement
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Paris :: OECD Publishing,, 2005.
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Nuclear Science,
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1 online resource (548 p. ;; 20x27cm.).
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| ISBN
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9789264011588
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| Contents
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Foreword -- Executive Summary -- Session Summaries -- Seminar Programme -- Session I. Opening and Industrial Goals -- Effect of PWR Re-Start Ramp Rate on Pellet-Cladding Interactions by S. K. Yagnik, D.J. Sunderland, and B. C. Chang -- Pellet-Cladding Mechanical Interaction in Boiling Water Reactors by M. Billaux and H. Moon -- PCI-Related Constraints on EDF PWRs and Associated Challenges by S. Beguin -- Review of Operational Requirements with Respect to PCMI in a VVER and the Corresponding Developments in the TRANSURANUS Code by by P. Van Uffelen, K. Lassman, A. Schubert, J. van der Laar, Cs. Gyori, D. Elenkov, and B. Hatala -- PCMI Implicatons for High Burn-Up Light Water Reactor Fuel in Reactivity-Initiated Accidents by C. Vitanza, J. M. Conde Lopez -- Session II. Fuel Material Behaviour in PCI Situation -- Physical Model Development for Prediction of Rim-Layer Formation in OU2 Fuel by V. V. Likhanskii, O. V. Khorushii, A. A. Sorokin -- Microstructure Investigations of As-Irradiated, Annealed, and Power Ramped High Burn-Up Fuel by S. K. Yagnik, J. A. Turnbull, and R. A. Gomme -- Effectof Thermal and Mechanical Properties of th eDUPIC Fuel on the Pellet-Cladding Mechanical Interaction by H-J. Ryu, K-H. Kang, C-J. Park, J-W Park, K-C. Song, and M-S. Yang -- Out-of-Pile and In-Pile Viscoplastic Behvaiour of Mixed Oxide Fuels by L. Caillot, C. Nonon, and V. Basini -- Mechanical Characterisation of Irradiated Fuel Materials with Local Ultrasonic Methods by D. Baron, D. Laux, and G. Despaux -- Fuel Swelling Importance in PCI Mechanistic Modelling by V. I. Arimescu -- Modelling of a Pellet-Clad Mechanical Interaction in LWR Fuel by Considering Gaseous Swelling by J-S. Cheon, Y-H. Koo, B-H. Lee, J-Y.- Oh, and D-S. Sohn -- The Reduction of Fission Gas Swelling through Irradiation-Induced Re-Solution by R. J. White -- On the Relations between the Fission Gas Behaviour and the Pellet-Cladding Mechanical Interaction in LSR Fuel Rods by P. Van Uffelon, M. Sheindlin, V. Rondinella, and C. Ronchi -- Session III. Cladding Behaviour Relevant to PCI -- Pellet-Cladding Interaction in VVER Fuel Rods by A. V. Smirnov, B. A. Kanashov, D. V. Markow, V. A. Ovchinikov, V. S. Ovchinikov, V. S. Polenok, and A. A. Ivashchenko -- Characterisation of Volatile Fission Products, Including Iodine, after a Power Ramp by L. Desgranges, B. Pasquet, X. Pujol, I. roure, Th. Blay, J. Lamongagne, Th. Martella, B. Lacrois, O. Comiti, L. Caillot -- Testing and Modelling Iodine-Induced Stress Corrosion Cracking in Stress-Relieved Zircaloy-4 by D. Le Boulch, L. Fournier, C. Sainte-Catherine -- Observation of a Pellet-Cladding Bonding Layer in High-Power Fuel by S. Van den Berghe, A. Leenaers, B. Vos, L. Sannen, M. Verwerft -- Cladding Liner Surface Effects and PCI by G. Lysell, K. Kitano, D. Schrire, and J-E. Lindback -- Session IV. In-Pile Rod Behaviour -- Results of WWER High Burn-Up Fuel Rod Examinations in the Process of and After Their Testing in the MIR Reactor under Power Cycling Conditions by A. V. Bouroukine, G. D. Lyadov, S. V. Lobin, V. A. Ovchinikov -- Ramp Testing of SBR MOX Fuel by M. Barker, P. Cook, R. Weston, G. Dassel, C. Ott, R. Stratton, D. Papaioannou, and C. Walker -- PCI Behaviour of Chromium Oxide-Doped Fuel by C. Nonon, J-C Menard, S. Lansiart, J. Noirot, S. Martin, G-M. Decroix, O. Rabouille, C. Delafoy, and B. Petitprez -- PCMI of High Burn-Up Fuel as Manifested by Different Types of Instrumentation and Measurements in the Halden Reactor Experimental Programme by W. Wiesenack and T. Tverberg -- Power Ramping in the OSIRIS Reactor: Database Analysis for Standard UO2 Fuel with Zy-4 Cladding by C. Mougel, B. Verhaeghe, C. Verdeau, S. Lansiart, S. Beguin, and B. Julien -- Experimental Data on PCI and PCMI within the IFPE Database by J.C. Killeen, E. Sartori, and J. A. Turnbull -- Session IV. Modelling of the Mechanical Interaction between Pellet and Cladding -- -Modelling the Effect of Oxide Fuel Fracturing on the Mechanical Behaviour of Fuel Rods by T. Helfer, P. Garcia, F. Sidoroff, J-M. Ricaud, and D. Plancq -- Crack and Dishing Evolution Models and PCI-SCC Considerations for Fuel Pellets in a Quasi-Bi-Dimensional Environment by A. C. Marino -- Non-Linear Behaviour of Multi-Phase MOX Fuels: A Micromechanical Approach by S. Rousette, J-M. Gatt, J-C. Michel -- The Mechanical Response of Cladding with a Hydride Lens under PCMI Loading Conditions by R. Montgomery, J. Rashid, R. Dunham, O. Ozer, S. K. Yagnik, and R. Yang -- Assessment of Cladding Relaxation and PCMI Models in INFRA by Y-M. Kim, Y-S. Yang, C-B. Lee, D-H. Kim, and Y-H. Jung -- Two-Dimensional (2-D) Pellet-Cladding Modelling using FEM at NRI Rex plc by M. Valach, and J. Zymak -- Modelling 3-D Mechanical Phenomena in a 1-D Industrial Finite Element Code: Results and Perspectives by V. Guicheret-Retel, F. Trivaudey, M. L. Boubakar, R. Masson, and Ph. Thevenin -- The COPERNIC Mechanical Model and its Application to Doped Fuel by C. Garnier, P. Mailhe, P. Vesco, L.C. Bernard, C. Delafoy, and P. Garcia -- Modelling of Thermal Mechanical Behaviour of High Burn-Up VVER Fuel at Poer Transients with Special Emphasis on the Impact of Fission Gas Induced Swelling of Fuel Pellets by V. Novikov, A. Medvedev, G. Khvostov, S. Bogatyr, V. Kuzetsov, and L. Korystin -- TOUTATIS: An application of the Cast3M Finite Element Code for PCI Three-Dimensional Modelling by F. Bentejac, and N. Hourdequin -- Methodology for Multi-Dimensional Simulation of Power Ramp Tests by C. Struzik, D. Plancq, B. Michel, P. Garcia, and C. Nonon. -- Modelling of Pellet-Clad Interaction during Power Ramps by G.Zhou, J. E. Lindback, H. C. Schutte, L. O. Jernkvist, and A. R. Massih -- List of Participants.
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| Abstract
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This report communicates the results of an international seminar which reviewed recent progress in the field of pellet-clad interaction in light water reactor fuels. It also draws a comprehensive picture of current understanding of relevant phenomena and their impact on the nuclear fuel rod, under the widest possible conditions. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels.
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Nuclear Energy.
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France.
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Nuclear Energy Agency.
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