Random Noise Techniques in Nuclear Reactor Systems

Uhrig, R.E.; Stapleton, C. A.

doi:10.1109/tns.1975.4328078

Cited by 87 publications

(48 citation statements)

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“…The extraction and use of information from noise signals originating within a nuclear power plant for assessing the operational status of the plant has been advocated for a number of years [11][12][13][14][15]. Reactor incidents that resulted in a partial loss of core mechanical integrity or of fuel element cooling has been reported where a conspicuous change in the nature of a randomly fluctuating variable preceded the incidents [16][17][18].…”

Section: Resultsmentioning

confidence: 99%

A system for unattended surveillance of nuclear reactor behavior

Gonzalez

Howington²

1977

1977 IEEE Conference on Decision and Control Including the 16th Symposium on Adaptive Processes and a Special Symposium on Fuzz

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A multivariate statistical pattern recognition system for reactor noise analysis is presented. The basi3 of the system is a transformation for decou-' pling correlated variables and algorithms for inferring probability density functions. The system is adaptable to a variety of statistical properties of the data, and it ha3 learning, tracking, updating, and dlmensionelity reduction capabilities. System design emphasizes control of the false-alarm rate. Its abilities to learn normal patterns and to recognize deviations from these patterns were evaluated by experiments at the OBIIL High-Flux Isotope Reactor. Power perturbations of less than 0.1)5 of the mean value in selected frequency ranges were readily detected by the pattern recognition system.

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Section: Resultsmentioning

confidence: 99%

A system for unattended surveillance of nuclear reactor behavior

Gonzalez

Howington²

1977

1977 IEEE Conference on Decision and Control Including the 16th Symposium on Adaptive Processes and a Special Symposium on Fuzz

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“…Active frequency analysis uses the amplitude and phase angle versus frequency response to an input signal (Uhrig 1970). The input signals can be white noise, pseudo random noise, or pulses.…”

Section: Frequency Analysismentioning

confidence: 99%

Evaluating the Effects of Aging on Electronic Instrument and Control Circuit Boards and Components in Nuclear Power Plants

Hannaman¹,

Wilkinson²

2005

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For the last three decades, MIL-HDBK-217 has been widely used to predict product reliability. In many cases the prediction model results are inaccurate when compared with subsequently measured mean time between failures in the field. One reason for the difference is because the aging theory used in the MIL-HDBK-217 and similar approaches typically assume a single longterm aging process that is related to a reaction rate. The aging process model is based on the original Arrhenius model, which is based on reaction rates in chemical mixtures. This model has been extended to the breakdown of insulation in electrical systems as the number of discharges increase over time. A temperature impact model has also been developed to address the increase in insulation breakdown at elevated temperature. The temperature model has been used to support accelerated reliability testing. Purpose of MIL-HDBK-217This military standard is used to estimate the inherent reliability of electronic equipment and systems, based on component failure data. It consists of two basic prediction methods:Parts-Count Analysis-Requires relatively little information about the system and primarily uses the number of parts in each category with consideration of part quality and environments encountered. Generally, the method is applied in the early design phase, where the detailed circuit design is unknown, to obtain a preliminary estimate of system reliability.Part-Stress Prediction-Updates the initial estimate with specific models for stress-analysis, environmental conditions, quality applications, maximum ratings, complexity, temperature, construction, and a number of other application-related factors. This method tends to be used near the end of the design cycle, after the actual circuit design has been defined. Failure Rate EquationsThe general failure rate model for a part in MIL-HDBK-217 is of the form:Where: h, = the base failure rate, is described by the Arrhenius equation, and ~C~~C E~C A . . . = factors related to component quality, environment, and application stressThe Arrhenius equation illustrates the relationship between insulation breakdown rate and temperature for components. It can be derived from the observed dependence of chemical reactions on temperature changes. A-1Application of Aging Theory E __ R ( t ) = AeWhere: R(T) = process rate (e.g., rate of discharge increase) E = activation energy for the process K = Boltzmann's constant T = absolute temperature A = a constant The activation energy for each component can vary, and example of activation energies is shown in Table A-1. This is a first order impact of the activation energy for failure mechanisms applicable to microcircuits (Livingston 2000). Application of Arrhenius Equation in AgingMIL-HDBK-217F provides measured data for each part type, such as microcircuits, transistors, resistors, and connectors. The failure rates of components that are determined by accelerated testing using a high temperature can be converted to an operational condition at a lower temperature, by u...

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“…Each technique has its own data analysis and experimental data collection method [7−18]. The endogenous (inherent) pulsed neutron source technique is a branch of correlation analysis of neutron counts in the time domain [3] (the third item in the above categories of ZPRN analysis). The basic principle of the technique is the conditional start of a multichannel scaler.…”

Section: Introductionmentioning

confidence: 99%

“…Correlation monitors have been used in different applications for measurement of physical parameters [21,22]. In reactor noise studies, the theory has been studied lately, and different apparatuses have been developed for ZPRN experiments [3][4]9]. Analogue monitors based on a single rate meter or two inter-compensated rate meters and digital monitors are also applied [16][17]23].…”

Section: Introductionmentioning

confidence: 99%

Development and Experimental Validation of a Correlation Monitor Tool Based on the Endogenous Pulsed Neutron Source Technique

Arkani

Khalafi

Vosoughi

et al. 2017

Metrology and Measurement Systems

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A correlation measuring tool for an endogenous pulsed neutron source experiment is developed in this work. Paroxysmal pulses generated by a bursts of neutron chains are detected by a 10-kbit embedded shift register with a time resolution of 100 ns. The system is implemented on a single reprogrammable device making it a compact, cost-effective instrument, easily adaptable for any case study. The system was verified experimentally in the Esfahan heavy-water zero power reactor (EHWZPR). The results obtained by the measuring tool are validated by the Feynman-α experiment, and a good agreement is seen within the boundaries of statistical uncertainties. The theory of the methods is briefly initiated in the text. Also, the system structure is described, the experimental results and their uncertainties are discussed, and neutron statistics in EHWZPR is examined experimentally.Keywords: endogenous pulsed neutron source experiment, neutron noise fluctuation, zero power reactor noise, Esfahan heavy-water zero power reactor, neutron correlation.

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Random Noise Techniques in Nuclear Reactor Systems

Cited by 87 publications

References 0 publications

A system for unattended surveillance of nuclear reactor behavior

A system for unattended surveillance of nuclear reactor behavior

Evaluating the Effects of Aging on Electronic Instrument and Control Circuit Boards and Components in Nuclear Power Plants

Development and Experimental Validation of a Correlation Monitor Tool Based on the Endogenous Pulsed Neutron Source Technique

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