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Formulation of the Problem. One problem of the analysis of the running safety level of the power-generating units of nuclear power plants, based on the implementation of the concept of a deeply stacked shielding, consists of assessment of the state and effectiveness of the initial levels of shielding provided by the barriers [1].A possible approach to the solution of this problem is to make a systematic analysis of the data on the disruptions of the normal operation of the power-generating unit and to calculate the probability that a disruption transforms into a serious accident associated with melting of the core. This parameter is called the disruption rating, and the sum of the disruptions ratings in the operation of the power-generating unit over some period of operation (for example, one month) is the safety rating of the unit for this period [2, 3].A methodology for performing a quantitative analysis of the running safety on the basis of the safety rating of a power-generating unit is presented in [2][3][4]. The present paper follows the same direction and expands the possibilities of the statistical analysis of the running safety.To construct a more concrete formulation of the problem, we shall now analyze the acts of disruptions of the operation of a power-generating unit. Each disruption carries definite information about the degree of safety of the unit. Once assimilated, these data increase or decrease the degree of confidence of an expert in the running safety. Therefore, one problem of processing information about disruptions can be formulated in terms of a systematic analysis of hypotheses [5]:before the power-generating unit starts up, information about the expected degree of safety is available on the basis of the results of a probability analysis of safety; this information can be structured in the form of disjoint hypotheses H I, H 2 ..... H k about the degree of running safety, an indicator of which is the safety rating;the hypothesis H l is that the average safety rating is equal to R1; the hypothesis H 2 is that the average safety rating is equal to R 2, and so on; and, one hypothesis is correct and it must be identified (singled out) according to the results of the analysis of the disruptions.This approach corresponds to an expert analysis of the running safety of a power-generating unit of a nuclear power plant within the framework of a safety analysis.Our objective in the present paper is to present a method for singling out the most likely hypothesis about the rating that corresponds best to the information about disruptions and to show that the method is effective in adopting expert decisions about the running safety of the power-generating unit.Description of the Method. Let H l, H 2 .... , H k be k disjoint hypotheses about the degree of running safety of the power-generating unit. The degree of safety is characterized by the average M(R) safety rating R, i.e., HI:M(R) = RI; HE:M(R ) = RE; ... Hk: M(R) = R k.Before starting the analysis, an expert, using intuition and information about...
Formulation of the Problem. One problem of the analysis of the running safety level of the power-generating units of nuclear power plants, based on the implementation of the concept of a deeply stacked shielding, consists of assessment of the state and effectiveness of the initial levels of shielding provided by the barriers [1].A possible approach to the solution of this problem is to make a systematic analysis of the data on the disruptions of the normal operation of the power-generating unit and to calculate the probability that a disruption transforms into a serious accident associated with melting of the core. This parameter is called the disruption rating, and the sum of the disruptions ratings in the operation of the power-generating unit over some period of operation (for example, one month) is the safety rating of the unit for this period [2, 3].A methodology for performing a quantitative analysis of the running safety on the basis of the safety rating of a power-generating unit is presented in [2][3][4]. The present paper follows the same direction and expands the possibilities of the statistical analysis of the running safety.To construct a more concrete formulation of the problem, we shall now analyze the acts of disruptions of the operation of a power-generating unit. Each disruption carries definite information about the degree of safety of the unit. Once assimilated, these data increase or decrease the degree of confidence of an expert in the running safety. Therefore, one problem of processing information about disruptions can be formulated in terms of a systematic analysis of hypotheses [5]:before the power-generating unit starts up, information about the expected degree of safety is available on the basis of the results of a probability analysis of safety; this information can be structured in the form of disjoint hypotheses H I, H 2 ..... H k about the degree of running safety, an indicator of which is the safety rating;the hypothesis H l is that the average safety rating is equal to R1; the hypothesis H 2 is that the average safety rating is equal to R 2, and so on; and, one hypothesis is correct and it must be identified (singled out) according to the results of the analysis of the disruptions.This approach corresponds to an expert analysis of the running safety of a power-generating unit of a nuclear power plant within the framework of a safety analysis.Our objective in the present paper is to present a method for singling out the most likely hypothesis about the rating that corresponds best to the information about disruptions and to show that the method is effective in adopting expert decisions about the running safety of the power-generating unit.Description of the Method. Let H l, H 2 .... , H k be k disjoint hypotheses about the degree of running safety of the power-generating unit. The degree of safety is characterized by the average M(R) safety rating R, i.e., HI:M(R) = RI; HE:M(R ) = RE; ... Hk: M(R) = R k.Before starting the analysis, an expert, using intuition and information about...
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