Fission Gas Behaviour in Water Reactor Fuels
Subtitle: Seminar Proceedings, Cadarache, France, 26-29 September 2000
By: Organisation for Economic Co-operation and Development and Nuclear Energy Agency
Contributors: Nuclear Energy Agency
Series: Nuclear science; Nuclear Science
Publisher: OECD Publishing
Published: 2002
Place of publication: Paris
Language: eng
Format: [electronic resource]:
Number of pages: 564
ISBN-13: 9789264196353
Subjects: Nuclear energy
Description: During irradiation, nuclear fuel changes volume, primarily through swelling. This swelling is caused by the fission products and in particular by the volatile ones such as krypton and xenon, called fission gas. Fission gas behaviour needs to be reliably predicted in order to make better use of nuclear fuel, a factor which can help to achieve the economic competitiveness required by today's markets. These proceedings communicate the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Table of contents: title: Foreword; title: Executive Summary; title: Session Summaries; title: Workshop Programme; title: Opening Session; title: -Welcome Address by C. Bonnet; title: Keynote Address: Industry Challenges and Expectations with Respect to Fission Gas Release by M. Lippens, D. Boulanger, and L. Mertons; title: Session 1. Feedback from Experience; title: -Fission Gas Release and Related Behaviours of BWR Fuel under Steady-State and Transient Conditions by H. Sakurai, M. Sasaki, O. Kubota, and T. Isogai; title: Fission Gas Release from High Burn-Up VVER-440 Fuel under Steady State and Transient Operation Conditions by A. Smirnov, B. Kanashov, S. Kuzmin, and F. Kryukov; title: Irradiation Test of DUPIC Fuel by K. C. Song, M. S. Yang, and H. S. Park; title: Fission Gas Release and Fuel Swelling at Burn-Ups Higher than 50 MWd/kgU by S. Bremier, C. T Walker, and R. Manzel; title: Studies on the Fission Gas Release Behaviour of BWR and Experimental MOX Fuel Elements by U. K. Viswanathan, S. Annantharaman, D. N. Sah, S. Chatterjee, K. C. Sahoo, and D. S. C. Purushotham; title: A Review of Fission Gas Release Data within the NEA/IAEA by J. A. Turnbull, P. Menut and E. Sartori; title: Session II. Basic Mechanisms; title: A Mechanistic Fission Gas Behaviour Model for UO2 and MOX Fuels by L .Noirot, Ph. Garcia, and C. Struzik; title: Modelling the Influence of the Athermal Open Porosity on Fission Gas Release in LWR Fuel by P. Van Uffelen; title: Modelling of Fission Gas Bubble Migration to Grain Boundaries during Post-Irradiation Annnealing in High Burn-Up UO2 by J. H. Evans; title: The Development of Grain Face Porosity in Irradiated Oxide Fuel by R. J. White; title: Influence of Grain Growth Kinetics on Fission Gas Release by M. Szuta; title: A Dynamic Model for the Fission Gas Induced Swelling in High Burn-Up Fuel under Fast Power Transient by E. Muller, F. Lemoine, and R. Saurel; title: Contribution of the Rim to the Overall Fission Gas Release: What Do Isotopic Analyses Reveal? by J. Noirot, L. Desgranges, and P. Marimbeau; title: Influence of Surface Rearrangement on Fission Gases Diffusion: How Can round Grains Contribute to Fission GAs Depletion in th eRim by L. Desgranges, N. Lozano, J. Noirot, B. Pasquet and G. Eminet; title: Rim Formation and Fission Gas Behaviour: Some Structure Remarks by J. Spino, D. Papaioannou, I Ray, and D.Baron; title: Study of the Atomic Rare Gas Bahviour by Ab Initio Calculations by T. Petit; title: Diffusion of Volatile Fission Products in Oxide Fuels Treated as Polycrystalline Materials by M. C. Paraschiv, A. Paraschiv, and V. V. Grecu; title: Modelling of Fuel Oxidation Behaviour in Operating Defective Fuel Rods by B. J. Lewis and B. Szpunar; title: Helium Behaviour in Spent UO2 and MOX Fuels by J. P. Piron, M. Pelletier, and J. Pavageau; title: On the Diffusion Coefficient of Caesium in UO2 Fuel by K. Lassmann, A. Schubert, J. van de laar, and C. T. Walker; title: Session III. Analytical Experiments; title: Grain Boundary Inventories of Kruypton in CANDU Fuel by R. S. Dickson, R. F. O'Connor, and D. D. Semeniuk; title: Partition of Grain Boundary and Matrix Gas Inventories: Results Obtained Using the ADAGIO Facility by S. Ravel, G. Eminet, E. Muller and l. Caillot; title: Modelling the Bahviour of Intergranular Fission Gas During Out-of-=Pile Annealing by S. Valin, A. Mocellin, G. Eminet, S. Ravel, and J-C. Joubert; title: Investigations on Radioactive and Stable Fission GAs Release Behaviour at the Halden Reactor by J. A. Turnbull and E. Kolstad; title: PIE.Modelling of Fission Gas Release froma Ringhals High Burn-Up Rod Bumped in Halden by K. Malen; title: Session IV. Industrial Modelling and Software Packages; title: Fission GAs MOdel of the Fuel Code SPHERE-3 by H. Wallin, L. A. Nordstrom, and Ch. Hellwig; title: Development of the Fission Gas Behaviour Model in the START-3 Code and its Experimental Support by Yu. K. Bibilashvili, A. V. medvedev, G. A. Khvostov, S. M. Bogatyr, and L. V. Korystine; title: Evaluation of Thermal, Mechanical, and Fission Gas Release Behaviour for BWR Fuel Rods with TETO by H. Hernandez Lopez; title: Mechanistic Modelling of Gaseous Fission Product Behaviour bgy V. D. Kanukova, O. V. Khoruzhii, S. Yu. Kourtschtov, V. V. Likanskii and L. V. Matveew; title: FRAMATONE Analysis of Fission Gas Release and Related Topics by L. C. Bernard, J. L. Jacoud and P. Vesco; title: Fission Gas Release at Extended Burn-Ups: Effect of Two-Dimensional Heat Transfer by M. Tayal, S. D. Yu, J.H.K. Lau; title: Macroscopic Fission GAs Release Model Applied ot Russian Fuel by N. Djourelov; title: Numerical Algorithms for Intragranular Diffusional Fission Gas Release Incorporated in the TRANSURANUS Code by K. Lassmann; title: A Comparative Study of Fission Gas Behaviour in UO2 and MOX Fuels Usingthe METEOR Fuel Performanc Code by C. Struzik, Ph. Garcia, and L. NoirotThe Jules Horowitz Reactor: Experimental Possibilities by P. Chantoin, A. Ballagny, F. Augereau, and L. Caillot; title: Fission GAs Release at High-Burn-Up: Beyond the Standard Diffusion Model by H. Landskron, F. Sontheimer, and M. R. Bilaux; title: List of Participants