Research reactor fuel assemblies (FAs) are designed for in-reactor neutron generation, required for scientific-research experiments in the field of nuclear physics, radiation biology and reactor physics and for commercial fabrication of radio-isotopic products.

During more half-century period of JSC NCCP activities a precious practical experience of handling nuclear materials has been accumulated, unique technologies have been developed, traditions to work mostly satisfying the Customer requirements. All this is realized in FAs for research reactors

RELIABILITY of FA is based on use of design decisions tested during successful operation in Russian and foreign reactors.

EFFICIENCY of FA use is provided thanks to developed heat removal surface, high uranium loading and high fuel burnup.

SIMPLE DESIGN ensures easy handling of FAs during loading-unloading operations.

Main structural of FA is a 3-layered seam-less tubular fuel element (FE) the middle layer of which is uranium fuel composition, peripheral layers - aluminium alloy claddings. FEs have different cross-section profiles. Using various profiles and various U mass in FE, it is possible to complete FA with the operating characteristics specified by Customers.

In the process of items evolution FA with rod-type FE (EK-10, S-36) developed to the second generation FA (WWR-M2, IRT-2M, MR, WWR-TS) with tubular FE with double side cooling. At present the plant produces FA of third generation with thin wall tubular FE (WWR-M5, IRT-3M, IWW-10). FE composition is also improved. Uranium concentration increase from 1.3 g/cm³ to 1.7 g/cm³ reached in the 70ies became possible thanks to transition from uranium-aluminium alloy composition to the fuel composition in the form of uranium dioxide dispersed in aluminium matrix. In the 80ies the fuel composition with uranium concentration 2.5 g/cm³ was mastered.

In the present time within the framework of international programs aimed at nuclear fuel enrichment reduction (down to 20% U-235), Novosibirsk chemical concentrates plant in cooperation with the nuclear branch research institutes have developed new designs and technologies of FE fabrication on the base of uranium-molybdenum alloy with total uranium concentration up to 5.4 g/cm³

The chemical-metallurgical complex integrated in the nuclear fuel production complex provides for processing, reprocessing and purification of various raw materials, wastes and own recycled materials to remove impurities. This technological process makes it possible to produce at JSC NCCP not only fuel assemblies but also different uranium compounds as commodity goods the technical characteristics specified by the customer.