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Reliability of the RBMK-1000 coolant flow measurement system
- Source :
- Nuclear Energy and Technology 5(1): 81-87, Nuclear Energy and Technology, Vol 5, Iss 1, Pp 81-87 (2019)
- Publication Year :
- 2019
- Publisher :
- National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), 2019.
-
Abstract
- 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.
- Subjects :
- 020209 energy
System of measurement
Nuclear engineering
Parametric reliability
02 engineering and technology
Coolant flow
lcsh:TK9001-9401
01 natural sciences
010305 fluids & plasmas
random process
random variables
mathematical time expectation
Nuclear Energy and Engineering
coolant flow measurement system
0103 physical sciences
0202 electrical engineering, electronic engineering, information engineering
lcsh:Nuclear engineering. Atomic power
RBMK
Environmental science
time between failures
exponential estimate
distribution function
Reliability (statistics)
Subjects
Details
- Language :
- English
- ISSN :
- 24523038
- Database :
- OpenAIRE
- Journal :
- Nuclear Energy and Technology
- Accession number :
- edsair.doi.dedup.....d4fd38e18be59b69a8fb2f3c98bbfdc1
- Full Text :
- https://doi.org/10.3897/nucet.5.34296