Mathematical methods in the qualimetrical determination of safety level of nuclear power plant

High safety level of Nuclear Power Plant can be obtained by as careful design of the plant as possible. It seems to be necessary to determine the safety level quantitatively and objectively. In the present practice of safety evaluation of nuclear power plant, the following safety analysis methods have been employed: deterministic safety determination and probabilistic safety analysis. All mentioned ways of analysis base on probability mathematics. In order to calculate the safety level the reliability coefficients of particular components of the nuclear power plant have to be known. This paper deals with an alternative method of safety level calculation named qualimetrical determination of safety level of the power plants. The nuclear rector safety is considered with special attention within this method. The mentioned method was proposed by Altmann for electric power plants and used with success for several years