Thermophysical properties affecting safety and performance of nuclear fuel

Improvement of the nuclear fuel exploitation has been one of the main objectives of reactor technology during the last decades. Today, in view of a sustainable nuclear energy production, development of advanced reactors re-proposes the choice of innovative fuel cycle concepts, in a context of greater expectations and more stringent requirements. From the experience gained in the past, a fuel research and development strategy can be devised, by which selected physical properties are taken as in-pile fuel performance indices.Uranium dioxide, by far the most important fuel used in power plants, proved from the very beginning to have good design-related properties as well as an excellent resistance to radiation damage. Therefore, increasingly higher performance was demanded concerning lifetime in current power reactors, maximum burn-up and safe operation. Yet, fuel test campaigns carried out in the last years have shown that at very high burn-ups, conditions are attained where radical restructuring processes take place in the UO2 lattice, irrespective of the irradiation regime of the fuel rods. This has led to an intense research activity on the effects of radiation damage on the thermophysical properties of the fuel. Energy and matter transport processes were found to be strongly affected by reactor irradiation, the in-pile performance of the fuel being governed by self-healing processes that can be only in part controlled.Furthermore, in the severe reactor accidents the fuel high temperature thermodynamic properties must comply with safety requirements to be satisfied under conditions which have been not yet explored. Therefore, their description and formulation for applications in different scenarios represent one of the main goals of the future research on advanced fuels.

[1]  S. Matsumoto,et al.  Physical and mechanical properties of fission-damaged UN , 1982 .

[2]  H. Matzke,et al.  Fission-enhanced self-diffusion of uranium in UO2 and UC , 1973 .

[3]  C. Ronchi,et al.  Effect of burn-up on the thermal conductivity of uranium dioxide up to 100.000 MWd t−1 , 2004 .

[4]  J. A. Turnbull,et al.  The distribution of intragranular fission gas bubbles in UO2 during irradiation , 1971 .

[5]  C. Ronchi,et al.  Mass Spectrometric Measurements of Fission Product Effusion from Irradiated Light Water Reactor Fuel , 1996 .

[6]  C. Ronchi,et al.  Equation of State of UO2 , 2001 .

[7]  Christian Duriez,et al.  Thermal conductivity of hypostoichiometric low Pu content (U,Pu)O2−x mixed oxide , 2000 .

[8]  M. Hirai,et al.  Effects of soluble fission products on thermal conductivities of nuclear fuel pellets , 1994 .

[9]  B. Cheynet,et al.  Progress in the thermodynamic modelling of the O–U binary system , 2002 .

[10]  W. Däppen The Equation of State , 1993 .

[11]  J. S. Perrin,et al.  Effects of radiation on materials , 1981 .

[12]  A. Dworkin,et al.  Diffuse transition and melting in fluorite and antifluorite type of compounds. Heat content of potassium sulfide from 298 to 1260.degree.K , 1968 .

[13]  R. Cahn Book Review: Physical metallurgy of reactor fuel elements. Published by the metals society, London. ix + 474 pp. 1975. £ 24 in UK; £ 30 overseas , 1976 .

[14]  H. Matzke Radiation enhanced diffusion in UO2 and (U, Pu)O2 , 1983 .

[15]  C. Ronchi,et al.  Laboratory Measurement of the Heat Capacity of Urania up to 8000 K: I. Experiment , 1993 .

[16]  K. Une,et al.  Rim structure formation and high burnup fuel behavior of large-grained UO2 fuels , 2000 .

[17]  H. Kleykamp,et al.  The chemical state of the fission products in oxide fuels , 1985 .

[18]  G. Ondracek Zum Zusammenhang zwischen Eigenschaften und Gefügestruktur mehrphasiger Werkstoffe Teil I: Zielsetzung, Kenntnisstand und stereologische Beschreibung der Gefügestruktur , 1977 .

[19]  C. Ronchi Physical processes and mechanisms related to fission gas swelling in MX-type nuclear fuels , 1979 .

[20]  C. Ronchi The nature of surface fission tracks in UO2 , 1973 .

[21]  C. Mathews,et al.  Thermal conductivity of rare earth-uranium ternary oxides of the type RE6UO12 , 2002 .

[22]  C. Ronchi On diffusion and precipitation of gas-in-solid , 1987 .

[23]  M. Hoch,et al.  The system U-UO3: Phase diagram and oxygen potential , 1986 .

[24]  T. Kirihara,et al.  Defects in uc single crystal due to fission damage , 1981 .

[25]  C. Ronchi,et al.  Thermodynamic model of solid non-stoichiometric uranium dioxide , 2006 .

[26]  C. Ronchi,et al.  Radiation re-solution of fission gas in uranium dioxide and carbide , 1986 .

[27]  C. Ronchi,et al.  Fission-Fragment Spikes in Uranium Dioxide. , 2002 .

[28]  Gerhard Ondracek,et al.  Zum Zusammenhang zwischen Eigenschaften und Gefügestruktur mehrphasiger Werkstoffe. Teil III: Gefügestruktur und Elastizitätsmodul , 1978 .

[29]  H. Matzke,et al.  The effect of fission spikes on fission gas re-solution , 1973 .

[30]  Aneesur Rahman,et al.  Correlations in the Motion of Atoms in Liquid Argon , 1964 .

[31]  C. Ronchi,et al.  Extrapolated equation of state for rare gases at high temperatures and densities , 1981 .

[32]  E. Kröner,et al.  Kontinuumstheorie der Versetzungen und Eigenspannungen , 1958 .

[33]  Hj. Matzke,et al.  Science of advanced LMFBR fuels , 1986 .

[34]  M. Coquerelle,et al.  The Sodium-Bonding Pin Concept for Advanced Fuels Part I: Swelling of Carbide Fuel up to 12% Burnup , 1983 .

[35]  Dario Manara,et al.  Melting of Stoichiometric and Hyperstoichiometric Uranium Dioxide , 2005 .

[37]  E. A. Fischer A New Evaluation of the Urania Equation of State Based on Recent Vapor Pressure Measurements , 1989 .

[38]  B. Abeles Lattice Thermal Conductivity of Disordered Semiconductor Alloys at High Temperatures , 1963 .

[39]  C. Ronchi,et al.  Premelting transition in uranium dioxide , 1993 .

[40]  R. E. Latta,et al.  Determination of solidus-liquidus temperatures in the uo2 + x system (−0.50 , 1970 .