Trends of Research
- Generation of experimental data and study of the mechanisms of changes in the fuel and structural materials properties under irradiation of different intensity;
- Study of cladding materials corrosion resistance under different water chemistry, fuel-to-cladding mechanical interaction and fission gas release from fuel elements of nuclear power facilities;
- Study of radioactive product release and migration from fuel and untight fuel elements of water-cooled power reactors;
- Investigation of properties and justification of the performance of new materials, technologies and designs during reactor tests of nuclear engineering items under conditions simulating the real ones;
- Development of advanced methods to accumulate and produce radiochemicals with the required specific activity for engineering and medical purposes.
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Areas of Activities
- Testing of dummy fuel elements containing compact and vibropacked MOX fuel to justify life characteristics including comparative assessment of their performance;
- Testing of prototype fuel elements containing uranium dioxide fuel in the metal matrix;
- Additional irradiation up to a high burnup of refabricated and full-size fuel elements for water-cooled power reactors followed by materials tests;
- Testing of tight and untight fuel elements with simulated cladding defects, as well as refabricated instrumented and full-size fuel elements with a different fuel burnup for water-cooled power reactors under steady-state and transient conditions (RAMP, power maneuvering), and design-basis RIA and LOCA;
- Testing of dummy fuel elements with different fuel compositions and cladding materials for water-cooled power reactors;
- Testing of structural materials to study the effect of irradiation on their mechanical properties;
- Study of high-density uranium fuel compositions as well as fuel elements and FAs based on such compositions to reduce nuclear research reactor fuel enrichment under RERTR.
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Promising Trends of Research
- Study of performance and behavior of structural and fuel materials for different nuclear facilities (power, propulsion, research, space, etc.) under the conditions simulating normal ones (steady-state and transient) and design-basis accidents;
- Study of untight fuel elements of water-cooled power reactors including fission gas release from fuel under steady-state and transient conditions and design-basis accidents;
- Development of test procedures and rigs as well as tests including instrumented ones for fuel and structural materials of new-generation nuclear power facilities;
- Research in support of reducing fuel enrichment in nuclear research reactors under RERTR;
- Development of procedures to provide, maintain and control water chemistry, as well as equipment decontamination for nuclear test and power reactors, and related experiments;
- Enhancement in accumulating different purpose radionuclides.
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