Reliability of the RBMK-1000 coolant flow measurement system
An analysis of statistical data of diagnostic measurements of two parameters determining the performance of the RBMK-1000 SHADR-8A flowmeters – the minimum value of the negative amplitude half-wave at the transistor flow measuring unit (TIBR) input and the mean-square deviation ove...
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doaj-385f6682263f48af8ed13ba13b6c983c2020-11-25T02:06:20ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382019-04-0151818710.3897/nucet.5.3429634296Reliability of the RBMK-1000 coolant flow measurement systemArkady I. Pereguda0Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University “MEPhI” 1 An analysis of statistical data of diagnostic measurements of two parameters determining the performance of the RBMK-1000 SHADR-8A flowmeters – the minimum value of the negative amplitude half-wave at the transistor flow measuring unit (TIBR) input and the mean-square deviation over the flowmeter ball rotation period – made it possible to develop a mathematical model of the flowmeter parametric reliability. This mathematical model is a random process, which is a superposition of two delayed renewal processes. Studying the flowmeter operational reliability model provides an exponential estimate of the probability that the parameters determining the flowmeter performance will not exceed the specified levels. Using the Bernoulli scheme and the probability-estimating relationship for the flowmeter performance parameters, it is possible to calculate the probability of failure-free operation of both a single reactor quadrant and the coolant flow measurement system. In addition, it becomes possible to estimate the quadrant failure rate. Important for practice is the possibility of predicting the number of failed flowmeters depending on the system operation time. An indicator of the system reliability can be the average number of failed flowmeters, the relation for which is given in the paper. All the research results were obtained without any additional assumptions about the random values distribution laws. The obtained results can be easily generalized for the cases when the vector dimension of the determining parameters is greater than two. The use of the results of this study is illustrated by calculated quantitative values of the flowmeter parametric reliability indicators and the coolant flow measurement system. https://nucet.pensoft.net/article/34296/download/pdf/ |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Arkady I. Pereguda |
spellingShingle |
Arkady I. Pereguda Reliability of the RBMK-1000 coolant flow measurement system Nuclear Energy and Technology |
author_facet |
Arkady I. Pereguda |
author_sort |
Arkady I. Pereguda |
title |
Reliability of the RBMK-1000 coolant flow measurement system |
title_short |
Reliability of the RBMK-1000 coolant flow measurement system |
title_full |
Reliability of the RBMK-1000 coolant flow measurement system |
title_fullStr |
Reliability of the RBMK-1000 coolant flow measurement system |
title_full_unstemmed |
Reliability of the RBMK-1000 coolant flow measurement system |
title_sort |
reliability of the rbmk-1000 coolant flow measurement system |
publisher |
National Research Nuclear University (MEPhI) |
series |
Nuclear Energy and Technology |
issn |
2452-3038 |
publishDate |
2019-04-01 |
description |
An analysis of statistical data of diagnostic measurements of two parameters determining the performance of the RBMK-1000 SHADR-8A flowmeters – the minimum value of the negative amplitude half-wave at the transistor flow measuring unit (TIBR) input and the mean-square deviation over the flowmeter ball rotation period – made it possible to develop a mathematical model of the flowmeter parametric reliability. This mathematical model is a random process, which is a superposition of two delayed renewal processes. Studying the flowmeter operational reliability model provides an exponential estimate of the probability that the parameters determining the flowmeter performance will not exceed the specified levels. Using the Bernoulli scheme and the probability-estimating relationship for the flowmeter performance parameters, it is possible to calculate the probability of failure-free operation of both a single reactor quadrant and the coolant flow measurement system. In addition, it becomes possible to estimate the quadrant failure rate. Important for practice is the possibility of predicting the number of failed flowmeters depending on the system operation time. An indicator of the system reliability can be the average number of failed flowmeters, the relation for which is given in the paper. All the research results were obtained without any additional assumptions about the random values distribution laws.
The obtained results can be easily generalized for the cases when the vector dimension of the determining parameters is greater than two. The use of the results of this study is illustrated by calculated quantitative values of the flowmeter parametric reliability indicators and the coolant flow measurement system.
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url |
https://nucet.pensoft.net/article/34296/download/pdf/ |
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