4 research outputs found
Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit
At the moment, 11 nuclear power plants (NPP) are under operation in the Russian Federation. More than half of the reactor units used are VVER-1000 reactors. NPP is a complex engineering structure consisting of plenty of complex equipment. Equipment operates under severe conditions: hard radiation, high temperatures, and high pressure. Nuclear reactor has a finite lifespan of 30 years. Most nuclear power plants based on VVER-1000 reactors have almost exhausted their lifespan. Therefore, these reactors require a life extension analysis. This paper demonstrates an analysis of brittle fracture strength for VVER-1000 reactor pressure vessel. According to the findings, calculated parameters do not outreach the 10 % limit
Mathematical modeling of combustion wave propagating in SH-synthesis of functional borides used to protect from mixed ionizing radiation
This work describes the mathematical model of SHS combustion wave propagating in the system of W-B. The model is based on the heat equation. The result of modelling is a forecast of SH-synthesis temperature regime in this system what allows forecasting a phase composition and thermal stresses. The model checking was realized in the experiment in the synthesis of this system in a laboratory-scale plant including the SHS reactor. The presented model is in agreement with the experiment in a maximum synthesis temperature and the curve rate of synthesis carrying out
Mathematical modeling of combustion wave propagating in SH-synthesis of functional borides used to protect from mixed ionizing radiation
This work describes the mathematical model of SHS combustion wave propagating in the system of W-B. The model is based on the heat equation. The result of modelling is a forecast of SH-synthesis temperature regime in this system what allows forecasting a phase composition and thermal stresses. The model checking was realized in the experiment in the synthesis of this system in a laboratory-scale plant including the SHS reactor. The presented model is in agreement with the experiment in a maximum synthesis temperature and the curve rate of synthesis carrying out
Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis
The paper describes a technique for obtaining intermetallic matrix materials based on Zr-Al and Ni-Al systems for dispersive nuclear fuel. This type of fuel is planned to be used in existing and future high-temperature nuclear reactors. Physical and mathematical modelling of the process of activation of matrices by neutron radiation showed that upon reaching the value of thermal neutron fluence of the order of 2.76Β·1021 nΒ·cm-2 , the activity of Zr-Al and Ni-Al matrices was 1.3Β·1010 and 0.2Β·1010 Bq/g, respectively. The analysis showed that in terms of exposure of irradiated fuel it is preferable to use a matrix based on the zirconium-aluminium system