Use of Batch Methods of Verification of Measurement Channels at Nuclear Power Plants
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GENERAL PROBLEMS OF METROLOGY AND MEASUREMENT TECHNIQUE USE OF BATCH METHODS OF VERIFICATION OF MEASUREMENT CHANNELS AT NUCLEAR POWER PLANTS
V. V. Zhmaylov, A. Yu. Kozhevnikov, and O. A. Korovina
UDC 681.2
The need for the development of additional regulatory documents for the purpose of increasing the economic efficiency in the operation of nuclear power plants and reducing the labor input involved in verification of their measurement channels is demonstrated. Regulation of provisions regarding means of verification of the measurement channels of nuclear power plants either componentwise or batchwise by means of basic and alternative methods depending on the requirements imposed on the reliability of the results of verification is proposed. Uniformly precise, cross, and compound methods are identified as alternative methods of batch verification. The basic problems that have to be solved in order to develop regulatory documents are identified and the requirements imposed on their basic provisions are presented. It is demonstrated that in existing regulatory documents regulation of provisions on the use of methods of batch verification of measurement channels at nuclear power plants will make it possible to control the error of a channel as a unified means of measurement without the need to dismantle the components, reduce the time needed for verification in the course of shut down of the power unit, and preserve the reliability of the results of verification of a measurement channel at an acceptable level. An example of a technique for estimating the reliability of methods of batch verification as one of the most important criteria for the selection of a verification method is presented. Keywords: nuclear power plant, verification of measurement channels, batch verification, basic method of batch verification, alternative methods of batch verification, cross method of batch verification, uniformly precise method of batch verification, compound method of batch verification, reliability of the results of verification, labor input of verification.
Introduction. According to existing regulatory documents for nuclear power plants, all measurement systems and measurement channels must be means of measurement of the approved type and undergo verification in batches, in a unified legal means of measurement, or componentwise (Federal Law No. 102-FZ, June 26, 2006, “On Assurance of the Uniformity of Measurements,” as amended on July 13, 2015; GOST R 8.596-2002, “State System for Ensuring the Uniformity of Measurements (GSI). Metrological Assurance of Measurement Systems. Basic Assumptions;” Order of the State Corporation for Nuclear Energy (Rosatom) No. 1/10-NPA, October 31, 2013, “Approval of Metrological Requirements Imposed on Measurements, Standard Measures of Units of Quantities, Calibration Specimens, Means of Measurements and their Constituent Parts, and Program Software, Techniques and Methods of Measurement Used in the Field of Nuclear Energy”) [1, 2]. At the present time, measurement channels at nuclear power
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