TL;DR: In this article, the experimental data on the synthesis, consolidation to dense pellets and property evaluation of titanium diboride (TiB2) carried out in laboratory scale was presented. And the powders were characterized by XRD, chemical analysis and laser particle size analyzer.
Abstract: Titanium diboride (TiB2) is one of the candidate materials for high temperature structural applications and also for control rod elements in high temperature nuclear reactors. This paper presents the experimental data on the synthesis, consolidation to dense pellets and property evaluation of TiB2 carried out in laboratory scale. TiB2 powder was prepared by the reduction of titanium oxide with boron carbide and carbon, purified by high temperature – high vacuum treatment and milled to obtain micron sized particles. The powders were characterized by XRD, chemical analysis and laser particle size analyzer. The reduction process was optimized for the production of titanium boride of ∼1 μm size median dia with oxygen, carbon and nitrogen contents close to 0.5% each. Studies on densification of TiB2 powders by hot pressing were conducted. Pellets with a high density of 97.56% ρth were prepared by hot pressing at 1800 °C. Hardness of this sample was measured as 26 GPa, fracture toughness as 5.3 MPa m1/2 and thermal conductivity as 59.44 W/m/K at 500 °C.
TL;DR: In this paper, the authors presented the examination results of absorber element dummies containing dysprosium titanate, irradiated in the SM reactor to the neutron fluence of 3.4×10 22 cm −2 (E > 0.1 MeV).
TL;DR: In this paper, a high temperature supercritical light water (SCLWR-H) was designed for assessing its technical feasibility and potential economic improvement, which is a once-through direct cycle.
TL;DR: In this paper, a new nuclear burnup strategy CANDLE was proposed, where shapes of neutron flux, nuclide densities and power density distributions remain constant but move to an axial direction.
TL;DR: In this paper, the main characteristics of Niobium-bearing zirconium alloys used for fabricating fuel element claddings of pressurized water reactors are considered.
Abstract: The main characteristics of niobium-bearing zirconium alloys used for fabricating fuel element claddings of pressurized water reactors are considered. It is shown that the high corrosion and radiation resistance of zirconium parts is provided by the chemical composition, structure, and phase composition of the alloys. The Zr – Nb alloys developed in Russia provide reliable operation of fuel elements and fuel rod arrays in active reactors and serve as a basis for new modifications.