The behavior of implanted deuterium in advanced lithium orthosilicate (Li4SiO4) pellets with addition of lithium metatitanate (Li2TiO3), and in reference Li4SiO4 pellets, has been investigated. Thermal desorption (TD) spectroscopy was used to study the deuterium interaction with radiation defects in materials. Computational evaluation of deuterium desorption within the framework of the diffusion-trapping model allowed to associate characteristics of experimental TD spectra with specific trapping sites in the material. It was found that deuterium desorption is limited mainly by intragranular diffusion of deuterium and its trapping by radiation defects associated with Li-vacancy traps. Deuterium gas release from both ceramics demonstrated similar trend indicating weak dependence of deuterium trapping behavior on phase composition. The change of the morphology and elemental composition of the pellets surface has been analyzed. SEM examination indicated that ion irradiation and subsequent thermal desorption annealing of two-phase ceramics leads to an increase in surface destruction processes.
Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the development of severe accidents at nuclear power plants were tested in the high-temperature water vapor environment. A comparative analysis of the corrosion resistance of these materials is presented, as well as the results of similar tests by the world’s leading scientists. Samples of 42CrNiМo alloy revealed the highest corrosion resistance at high temperatures in a water vapor environment among the alternative materials for the fuel rod cladding considered in the study. The corrosion resistance of this alloy at a temperature of 1200 °C is approximately 40 times higher than that of Cr18Ni10Тi steel and E110 alloy. The high-temperature corrosion rate of the 42CrNiМo alloy is comparable to the corrosion rate of the Fechral alloy. The hydrogen that would be released during the oxidation of the 42CrNiМo alloy claddings would be almost forty times less compared to the zirconium alloy under the conditions of severe design accidents associated with overheating of the core.
The wear rate of titanium alloys VT1-0, TC5, VT6, VT14, OT4 under the action of microshocks due to cavitation, which is created in distilled water under the surface of the ultrasonic wave emitter, were determined. It was found that the increase in hardness and improvement of cavitation wear resistancefor these alloys depends on the alloying elements, and is also increased after heat treatment and ion-plasma modification of the sample surface. Although no unambiguous correlation was found between the structural class of the alloys and their cavitation wear. Due to ion-plasma modification of alloys, the cavitation wear resistanceis increased by several times, in particular, the VT6 alloy by 3 times. The phase composition of the samples before and after ion-plasma modification was studied and it was found that alloy resistance to cavitation significantly depends on it.
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