HTGR Measurements and Instrumentation Systems

Holcomb, David Eugene; Çetiner, Sacit M.

doi:10.2172/1040751

Cited by 12 publications

(6 citation statements)

References 61 publications

(44 reference statements)

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“…Currently there are no specific criteria related to I&C for HTR-10. However since this system will be operated in a high temperature environment, there is important attention need to be concerned; and there are information need to collect for developing criteria to measure the qualification of hardware and software related to I&C system [13]. Fig.…”

Section: Instrumentation and Control System For Htr-10mentioning

confidence: 99%

“…In general, the instrumentation of HTGR is not different from that of Pressurized Water Reactor (PWR). However, considering the position of the steam generator in the HTGR which is located on the primary circuit, it will have a little effect on the I&C requirements, because the secondary (water) side operating pressure is higher than the helium coolant pressure [13].…”

Section: Instrumentation and Control System For Htr-10mentioning

confidence: 99%

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Requirement Analysis of Computer-Based Instrumentation and Control System for Reaktor Daya Eksperimental

2019

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Developing and licensing of digital Instrumentation and control (I&C) system for nuclear power plant (NPP) are challenging especially for the new construction since digital technology are composite with a very high complexity of many integrated systems. National Nuclear Energy Agency of Indonesia (BATAN), who design Reaktor Daya Eksperimental (RDE), should prepare the documents to meet the licensing requirements of national regulator in this case Nuclear Energy Regulatory Agency of Indonesia (BAPETEN). BAPETEN’s chairman regulation No.6 year of 2012 is the first national requirement which state requirements related to design of computer-based system concerning on safety of power reactor that should be followed. Since BAPETEN only denotes requirements without state which code and standards to be used, therefore BATAN can add references from International Nuclear Energy Agency (IAEA) guidelines. In this paper, requirement document traceability is developed to determine which code and standards should be used to verify and validate the I&C computer-based system of RDE. The hierarchy of regulatory and utility requirements are developed to guide the design basis documentation. Developing requirements analysis of computer-based I&C system RDE are completed after determining the design requirements from the utility and regulatory requirements. This methodology will help the design engineers to follow the utility requirements by concerning to the production, and follow the regulatory requirements concerning the safety aspect.Keywords: Computer-based system, I&C System, Requirements analysis, Licensing, RDE

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Section: Instrumentation and Control System For Htr-10mentioning

confidence: 99%

Section: Instrumentation and Control System For Htr-10mentioning

confidence: 99%

Requirement Analysis of Computer-Based Instrumentation and Control System for Reaktor Daya Eksperimental

2019

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“…A method of ultrasonic thermometry is also discussed based on measurements of the velocity of ultrasound in a foreign probe inserted into the media of interest. Ball et al (2012) provide an overview of several emerging measurement technologies with potential application to high-temperature gas reactors (HTGRs). Several temperature measurement devices are discussed including Johnson noise thermometry, foreign probe-type ultrasonic thermometry, fiber-optic temperature sensors, and Au-Pt thermocouples.…”

Section: 4mentioning

confidence: 99%

A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants

Coble¹,

Meyer²,

Ramuhalli³

et al. 2012

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Currently in the United States, periodic sensor recalibration is required for all safety-related sensors, typically occurring at every refueling outage, and it has emerged as a critical path item for shortening outage duration in some plants. Online monitoring can be employed to identify those sensors that require calibration, allowing for calibration of only those sensors that need it. International application of calibration monitoring has shown that sensors may operate for longer periods within calibration tolerances. This issue is expected to also be important as the United States looks to the next generation of reactor designs (such as small modular reactors and advanced concepts), given the anticipated longer refueling cycles, proposed advanced sensors, and digital instrumentation and control systems. The U.S. Nuclear Regulatory Commission (NRC) accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no U.S. plants have been granted the necessary license amendment to apply it. This report presents a state-of-the-art assessment of online calibration monitoring in the nuclear power industry, including sensors, calibration practice, and online monitoring algorithms. This assessment identifies key research needs and gaps that prohibit integration of the NRC-approved online calibration monitoring system in the U.S. nuclear industry. Several needs are identified, including an understanding of the impacts of sensor degradation on measurements for both conventional and emerging sensors; the quantification of uncertainty in online calibration assessment; determination of calibration acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and assessment of the feasibility of using virtual sensor estimates to replace identified faulty sensors in order to extend operation to the next convenient maintenance opportunity. v Summary Transmission of accurate and reliable measurements is central to safe, efficient, and economic operation of nuclear power plants (NPPs). Current instrument channel calibration practice in the United States utilizes periodic assessment and adjustment, if necessary, of sensors to maintain sensor calibration within some prescribed tolerance. In performing calibration, intrusive techniques are used to determine the calibration condition-instruments are isolated from the system, sometimes through physical removal, and exercised through a series of known inputs. This sensor performance assessment is performed periodically, as required by the plant technical specifications (TS). Non-safety-related sensors also undergo recalibration, although not as frequently. Typically, calibration occurs during refueling outages (about every two years). The current approach to sensor calibration in operating light water reactors is expensive and time consuming, resulting in longer outages, increased maintenance cost, and additional radiation exposure to maintenance personnel, and it can be counterproductive, introducing e...

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“…The performance test results show that individual sensors can measure the changes in real-time. Ball et al ( 2012 ) described several measurement technologies with potential application to gas reactors. Among these, an optical-based pressure sensor based on the trajectory of the light in glass is analyzed.…”

Section: Introductionmentioning

confidence: 99%

Automatic Fracture Characterization Using Tactile and Proximity Optical Sensing

et al. 2020

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This paper demonstrates how tactile and proximity sensing can be used to perform automatic mechanical fractures detection (surface cracks). For this purpose, a custom-designed integrated tactile and proximity sensor has been implemented. With the help of fiber optics, the sensor measures the deformation of its body, when interacting with the physical environment, and the distance to the environment's objects. This sensor slides across different surfaces and records data which are then analyzed to detect and classify fractures and other mechanical features. The proposed method implements machine learning techniques (handcrafted features, and state of the art classification algorithms). An average crack detection accuracy of ~94% and width classification accuracy of ~80% is achieved. Kruskal-Wallis results (p < 0.001) indicate statistically significant differences among results obtained when analysing only integrated deformation measurements, only proximity measurements and both deformation and proximity data. A real-time classification method has been implemented for online classification of explored surfaces. In contrast to previous techniques, which mainly rely on visual modality, the proposed approach based on optical fibers might be more suitable for operation in extreme environments (such as nuclear facilities) where radiation may damage electronic components of commonly employed sensing devices, such as standard force sensors based on strain gauges and video cameras.

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HTGR Measurements and Instrumentation Systems

Cited by 12 publications

References 61 publications

Requirement Analysis of Computer-Based Instrumentation and Control System for Reaktor Daya Eksperimental

Requirement Analysis of Computer-Based Instrumentation and Control System for Reaktor Daya Eksperimental

A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants

Automatic Fracture Characterization Using Tactile and Proximity Optical Sensing

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