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Uranium Dioxide Properties


Investigation Properties of Uranium Dioxide Advanced and Mixed Uranium-Plutonium fuels (MOX) for Prediction of Performance and Operating Characteristics to Provide Certification Fuel and Verification of Computational Models for Parameters Definition of Ox

Tech Area / Field

  • FIR-FUE/Reactor Fuels and Fuel Engineering/Fission Reactors

3 Approved without Funding

Registration date

Leading Institute
All-Russian Scientific Research Institute of Non-Organic Materials named after A. Bochvar, Russia, Moscow

Supporting institutes

  • MIFI, Russia, Moscow\nNIIAR (Atomic Reactors), Russia, Ulianovsk reg., Dimitrovgrad


  • European Commission / Joint Research Center / Institute for Transuranium Elements, Germany, Karlsruhe\nFragema, France, Lyon

Project summary

The Project #534, as a whole, is directed at the implementation of analytical and experimental examinations of physic-mechanical and thermos-physical properties, as well as the composition and the structure of uranium dioxide (“advanced” – upgraded in terms of ductile characteristics) and U-Pu dioxide mixed (MOX) fuel. This aim include:

– correction the data base for designing of the fuel elements (FEs) for the cores of operating and future power reactors;

– development of methodical and technical basis for certification and licensing of the FEs;
– verification of computer codes and models evaluating FEs serviceability under conditions of high-level burn-up.

The 1st stage has been approved for funding in 1997 (1/3 of the total scope) and completed with the following results::

– the development and updating of the equipment and methods for examining properties, composition and structure of advanced U dioxide and mixed U-Pu dioxide irradiated fuel with burn-up up to 60-70 MW×day/kg U;

– experimental and analytical studies of standard U dioxide fuel, irradiation-induced re-sintering, densification and creep of the advanced U dioxide fuel;

– development of approaches for suppressing the fuel swelling;

– examinations of the structure, porosity, elemental composition, and properties (density, microhardness, and thermal capacity) of standard WWER fuel at high-level burn-up up to 65 MW×day/kg U, as well as analysis of other characteristics of the WWER fuel after the in-reactor experiments (nuclear compositions, etc);

– the development and verification of computer models and codes, including laboratory, in-pile, and out-of-pile experiments.

The Second Stage of the #534 Project is based on the developed methods and includes the set of analytical, methodical and experimental examinations, including in-reacor tests in NIIAR (Dimitrovgrad), which will allow to complete the main part of the planned complex of investigations. The principal properties of dioxide U and irradiated MOX-fuel as well will be measured and evaluated at the range of burn-up up to 70 MW×day/kg U. It is planning:

– to systematize, analyze and generalize the experimental results obtained on the WWER spent uranium fuel irradiated up to the burn-up of 60-70 MW×day/kg U;

– to perform in-reactor experimental and desk studies to generalize the data and to predict MOX-fuel performance in operational conditions;
– to study the structure, composition, mechanical and thermophysical properties of MOX-fuel irradiated to 40 MW×day/kg U, Pu;
– to extend the calculated models, developed for radiation-induced creep and densification of Uranium dioxide, on to the MOX fuel, and verify them;
– to elaborate the alternative technology for preparation of U and U-Pu dioxide test specimens;·
– to develop of methodical and technical support (technical data, documents) for certification and licensing of Uranium and MOX fuel and fuel elements.