Gateway for:

Member Countries

Fuel Elements for Water-Cooled Reactors


Creation of New Fuel Elements Generation for Water-Cooled Power Reactors of Different Purposes.

Tech Area / Field

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

8 Project completed

Registration date

Completion date

Senior Project Manager
Tocheny L V

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


  • COGEMA, France, Velizy\nImatran Voima (IVO), Finland, Helsinki\nFRAMATOME, France, Paris La Défense\nNuclear Power Engineering Corporation, Japan, Tokyo\nBelgonucléaire, Belgium, Mol\nEDF, France, Paris

Project summary

The development of fuel element of a new type with increased reliability and higher technical and economical indicators is the objective of the Project. For example, this new fuel element can be operated in a basic and in a transient mode with service life up to 10 years and burn-up 150,000 MWd/ton in VVER-type reactors. A container type fuel elements with uranium dioxide fuel being currently used are designed for three-year cycle and maximum burn-up 44,000 MWd/ton.

Within this Project we’ll develop a dispersal fuel element with a high uranium density fuel (for example U3Si, ZN-10, OM-9, etc) dispersed in porous and non-porous low melting point matrix alloys.

The use of filling, capillary filling, and extraction technologies allow to fabricate fuel element of any shape. Therefore, practically all fuel elements constructive solutions for nuclear reactors available and perspective ones with coolant temperature up to 350 °C can be provided.

Fuel core uranium density can varies within a wide range (up to 9 g/cm3) and, thus, meet different requirements as deep burn-up in a fuel core volume unit, high power intensity, low enrichments, etc.

The lengthening of fuel elements cycle will be of great economic benefit due to the save of uranium-235 and decrease of waste amount for reprocessing, that is also very important for the environmental control.

Additional benefits: low temperature in the center of fuel element core and no gas swelling, high corrosion resistance, serviceability under transient mode. Increased surface of heat removal due to the possibility of using cladding of various shapes.

By the end of the Project we are to develop the complete laboratory technologies and to produce the prototypes of fuel elements.