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
All-Russian Scientific Research Institute of Non-Organic Materials named after A. Bochvar, Russia, Moscow
- 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 summaryThe 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.
The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.
ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.