UO 2 has a long history being used as a nuclear fuel. However, its low thermal conductivity
has become one of the major concerns limiting nuclear reactor performance and safety …

The paper presents the results of studying the effect of irradiation with 85 MeV Fe 7+ ions on
the optical and structural properties of nitride ceramics at an irradiation temperature of 300 …

Ceramic material is one of the essential materials used in reactors. Beryllium oxide ceramics
have good high-temperature radiation stability, high density, high strength, and thermal …

The paper presents the results of research on changes in structural properties of BeO
ceramics under heavy ion irradiation and post-radiation annealing. Irradiation was carried …

The study of changes in physical-chemical and mechanical properties of ceramic nitride
materials as a result of the effect of heavy ions is of great interest in the field of radiation …

Based on the supercritical water-cooled reactor fuel assembly, a 19-rod bundle physical
model with a hexagonal outer casing is established, and the four-wire structure is added to …

ZrO 2 is one of the candidate materials for the matrix of inert matrix fuels because of its
excellent chemical stability and irradiation resistance. In this paper, the low thermal …

The paper presents the results of studying the effect of irradiation of Fe 7+ ions with an
energy of 1.5 MeV/nucleon on structural properties of AlN ceramics at an irradiation …

High thermal conductivity additives are being considered to create composite nuclear fuels
with a higher effective thermal conductivity (ETC) to reduce the peak fuel temperatures …

UO2-BeO fuel, a quite potential accident tolerant fuel, is used to increase the temperature
margin of UO2 fuel and improve the safety performance of reactor operation. With the …