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Journal articles on the topic 'Nuclear reactor monitoring'

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Author: Grafiati

Published: 10 December 2022

Last updated: 28 January 2023

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1

Ali, R. A., S. L. Garrett, J. A. Smith, and D. K. Kotter. "Thermoacoustic thermometry for nuclear reactor monitoring." IEEE Instrumentation & Measurement Magazine 16, no. 3 (June 2013): 18–25. http://dx.doi.org/10.1109/mim.2013.6521130.

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2

Mesquita, A. Z., H. C. Rezende, A. A. C. Santos, and V. V. A. Silva. "DEVELOPMENT OF METHODS FOR MONITORING AND CONTROLLING POWER IN NUCLEAR REACTORS." Revista de Engenharia Térmica 13, no. 1 (June 30, 2014): 24. http://dx.doi.org/10.5380/reterm.v13i1.62064.

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Power monitoring of nuclear reactors is normally done by means of neutronic instruments, i.e. by the measurement of neutron flux. The greater the number of channels for power measuring the greater is the reliability and safety of reactor operations. The aim of this research is to develop new methodologies for on-line monitoring of nuclear reactor power using other reliable processes. One method uses the temperature difference between an instrumented fuel element and the pool water below the reactor core. Another method consists of the steady-state energy balance of the primary and secondary reactor cooling loops. A further method is the calorimetric procedure whereby a constant reactor power is monitored as a function of the temperature-rise rate and the system heat capacity. Another methodology, which does not employ thermal methods, is based on measurement of Cherenkov radiation produced within and around the core. The first three procedures, fuel temperature, energy balance and calorimetric, were implemented in the IPR-R1 TRIGA nuclear research reactor at Belo Horizonte (Brazil) and are the focus of the work described here. Knowledge of the reactor thermal power is very important for precise neutron flux and fuel element burnup calculations. The burnup is linearly dependent on the reactor thermal power and its accuracy is important in the determination of the mass of burned 235U, fission products, fuel element activity, decay heat power generation and radiotoxicity. The thermal balance method developed in this project is now the standard methodology used for IPR-R1 TRIGA reactor power calibration and the fuel temperature measuring is the most reliable way of on-line monitoring of the reactor power. This research project primarily aims at increasing the reliability and safety of nuclear reactors using alternative methods for power monitoring.

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3

Mesquita, Amir Zacarias, Daniel Artur Pinheiro Palma, Hugo Cesar Rezende, Alexandre Melo De Oliveira, Alexandre Melo De Oliveira, Youssef Morghi, Patrícia Albernaz Melo Ribeiro, Valéria Emiliana Alcântara e. Alves, and Diva Godoi de Oliveira Peconick. "Power Measurement Methodologies for Pool Nuclear Research Reactors." Latin American Journal of Development 3, no. 2 (May 3, 2021): 882–92. http://dx.doi.org/10.46814/lajdv3n2-032.

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Redundancy and diversity are two important criteria for power measurement in nuclear reactors. Other criteria such as accuracy, reliability and response speed are also of major concern. Power monitoring of nuclear reactors is normally done by means of neutronic instruments, i.e. by the measurement of neutron flux. The greater the number of channels for power measuring the greater is the reliability and safety of reactor operations. The aim of this research is to develop new methodologies for on-line monitoring of nuclear reactor power using other reliable processes. One method uses the temperature difference between an instrumented fuel element and the pool water below the reactor core. Another method consists of the steady-state energy balance of the primary and secondary reactor cooling loops. A further method is the calorimetric procedure whereby a constant reactor power is monitored as a function of the temperature-rise rate and the system heat capacity. Another methodology, which does not employ thermal methods, is based on measurement of Cherenkov radiation produced within and around the core. The first three procedures, fuel temperature, energy balance and calorimetric, were implemented in the IPR-R1 Triga nuclear research reactor at Belo Horizonte (Brazil) and are the focus of the work described here. Knowledge of the reactor thermal power is very important for precise neutron flux and fuel element burnup calculations. The burnup is linearly dependent on the reactor thermal power and its accuracy is important in the determination of the mass of burned 235U, fission products, fuel element activity, decay heat power generation and radiotoxicity. The thermal balance method developed in this project is now the standard methodology used for IPR-R1 Triga reactor power calibration and the fuel temperature measuring is the most reliable way of on-line monitoring of the reactor power. This research project primarily aims at increasing the reliability and safety of nuclear reactors using alternative methods for power monitoring.

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4

Katsioulas, I., I. Savvidis, and C. Eleftheriadis. "Nuclear Reactor Neutrino Detection with the Spherical Proportional Counter." HNPS Proceedings 21 (March 8, 2019): 92. http://dx.doi.org/10.12681/hnps.2010.

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Nuclear Power Reactors are the most powerful neutrino sources as they emit large numbers of antineu- trinos, at energies up to 10 MeV. The reactor neutrino detection is very important for fundamental physics goals, as well as for applications, among them being the possibility to determine the isotopic composition of the reactor’s core. This could lead to application of neutrino spectroscopy for reactor monitoring, either for improving the reliability of operation of power reactors or as a method to accomplish certain safeguard and non-proliferation objectives. We present here the conditions on detecting neutrinos coming from nuclear reactors with the Spherical Proportional Counter (SPC), by exploiting the coherent neutrino-nucleus elastic scattering.

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5

Jirsa, Pavel. "Monitoring of the VVER nuclear reactor internals." Nuclear Engineering and Design 168, no. 1-3 (May 1997): 1–9. http://dx.doi.org/10.1016/s0029-5493(96)01323-4.

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6

Vivier, Matthieu. "The Nucifer demonstrator for nuclear reactor monitoring." Journal of Physics: Conference Series 1216 (April 2019): 012005. http://dx.doi.org/10.1088/1742-6596/1216/1/012005.

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7

Harahap, Muhammad Rifqi. "Identifikasi kebutuhan sarana-prasarana pemantauan radiasi nirawak dalam pengawasan radiasi reaktor riset di Indonesia." Jurnal Pengawasan Tenaga Nuklir 1, no. 2 (December 15, 2021): 20–30. http://dx.doi.org/10.53862/jupeten.v1i2.015.

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The facility’s licensee conducts environmental radiation monitoring in nuclear facilities to monitor radiation exposure in the facility’s vicinity. This activity is carried out also to monitor radiation release as a result of nuclear reactor operation. Aside from that, monitoring also works as a device to monitor radioactive release in a nuclear emergency. Therefore, the radiation monitoring system is crucial in nuclear utilization facilities to determine the number of radiation exposure to the surrounding environment. However, the existing stationary monitoring system has a risk of being unable to work if the system is down in case of natural disaster occurs. One way to mitigate this risk is to deploy an unmanned radiation monitoring system to monitor radiation exposure without putting personnel at risk. To define a suitable unmanned radiation monitoring system, identification of facilities and infrastructure required to design an unmanned radiation monitoring system for a research reactor in Indonesia is carried out. Facilities and infrastructure needed for unmanned radiation monitoring systems are unmanned aerial vehicles, radiation detector, control and communication module, navigation system, and software for the control system. These required facilities and infrastructure are then specified to determine the necessary specification for monitoring research reactor in Indonesia. The facilities’ required specifications are unmanned aerial vehicles with rotary-wing type, CdZnTe Detector, and GPS/GLONASS based navigation system. For infrastructure specification, control and communication module and software for the control system is not specified in how the system could meet the expected required performance rather than in detail. However, the system must provide and process measurement data in real-time to be presented in a radiation heatmap. Keywords: Identification, Radiation Monitoring, Unmanned

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8

Erickson, Anna, and Christopher Stewart. "Monitoring of nuclear reactors with antineutrinos: comparison of advanced reactor systems." Journal of Physics: Conference Series 1216 (April 2019): 012018. http://dx.doi.org/10.1088/1742-6596/1216/1/012018.

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9

Bonivento, Claudio, Michael J. Grimble, Leonardo Giovanini, Mattia Monari, and Andrea Paoli. "Monitoring a gas-cooled nuclear reactor core integrity." IFAC Proceedings Volumes 41, no. 2 (2008): 12953–58. http://dx.doi.org/10.3182/20080706-5-kr-1001.02190.

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10

Bernstein, A., Y. Wang, G. Gratta, and T. West. "Nuclear reactor safeguards and monitoring with antineutrino detectors." Journal of Applied Physics 91, no. 7 (April 2002): 4672–76. http://dx.doi.org/10.1063/1.1452775.

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11

Gribov, I. V., M. B. Gromov, G. A. Lukjanchenko, G. J. Novikova, B. A. Obinyakov, A. Y. Oralbaev, M. D. Skorokhvatov, S. V. Sukhotin, A. S. Chepurnov, and A. V. Etenko. "iDREAM: an industrial detector for nuclear reactor monitoring." Journal of Physics: Conference Series 675, no. 1 (February 5, 2016): 012031. http://dx.doi.org/10.1088/1742-6596/675/1/012031.

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12

Sweany, M., J. Brennan, B. Cabrera-Palmer, S. Kiff, D. Reyna, and D. Throckmorton. "Above-ground antineutrino detection for nuclear reactor monitoring." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 769 (January 2015): 37–43. http://dx.doi.org/10.1016/j.nima.2014.09.073.

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13

Potapenko, I. T. "Three-dimensional harmonic monitoring of a nuclear reactor." Soviet Atomic Energy 67, no. 6 (December 1989): 928–31. http://dx.doi.org/10.1007/bf01124971.

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14

ÖZTÜRK, Sertaç, Aytül ADIGÜZEL, Veysi Erkcan ÖZCAN, and N. Gökhan ÜNEL. "Monitoring Akkuyu nuclear reactor using antineutrino flux measurement." TURKISH JOURNAL OF PHYSICS 41 (2017): 41–46. http://dx.doi.org/10.3906/fiz-1604-20.

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15

Ozturk, Sertac, Aytul Adiguzel, V. Erkcan Ozcan, and Gokhan Unel. "Monitoring Akkuyu Nuclear Reactor Using Antineutrino Flux Measurement." Journal of Physics: Conference Series 1216 (April 2019): 012022. http://dx.doi.org/10.1088/1742-6596/1216/1/012022.

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16

Giraud, A., and J. Veau. "Full Autonomous Monitoring Tools Inside Nuclear Reactor Building." IEEE Transactions on Nuclear Science 57, no. 5 (October 2010): 2662–69. http://dx.doi.org/10.1109/tns.2010.2046647.

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17

Lhuillier, D. "Reactor neutrino monitoring." Nuclear Physics B - Proceedings Supplements 188 (March 2009): 112–14. http://dx.doi.org/10.1016/j.nuclphysbps.2009.02.025.

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18

Adams, James P., Glenn E. McCreery, and Jong H. Kim. "Monitoring Pressurized Water Reactor Transients Using Reactor Coolant Pumps." Nuclear Science and Engineering 109, no. 4 (December 1991): 325–40. http://dx.doi.org/10.13182/nse91-a23858.

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19

Ozturk, Sertac. "Nuclear reactor monitoring with gadolinium-loaded plastic scintillator modules." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 955 (March 2020): 163314. http://dx.doi.org/10.1016/j.nima.2019.163314.

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20

Lei, Qingxin, Chenyu Shan, and Wenzhang Xie. "Overall design of radiation monitoring system formaritime nuclear facilities." E3S Web of Conferences 252 (2021): 03025. http://dx.doi.org/10.1051/e3sconf/202125203025.

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The Radiation Monitoring System (RMS) is designed to check continuously the reactor at the operating set points, it assures that no individual and persons receive an unnecessary or hazardous exposure to radiation. According to the process and operation characteristics of Small Modular Reactor (SMR), these radiation monitoring channels can be grouped into the process radiation monitoring subsystem, the effluent radiation monitoring subsystem, the area radiation monitoring subsystem and the Post Accident Monitoring Subsystem (PAMS). Based on the architecture design of RMS, the demand of signal interface and power interface is analysed. Through introducing the marine environment, the problems of anti-shock, vibration, inclination and swing of loads are put forward.

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21

Ruddy, Frank H., Abdul R. Dulloo, John G. Seidel, Frederick W. Hantz, and Louis R. Grobmyer. "Nuclear Reactor Power Monitoring Using Silicon Carbide Semiconductor Radiation Detectors." Nuclear Technology 140, no. 2 (November 2002): 198–208. http://dx.doi.org/10.13182/nt02-a3333.

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22

Pang, Y., L. Giovanini, M. Monari, and M. Grimble. "Condition monitoring of an advanced gas-cooled nuclear reactor core." Proceedings of the Institution of Mechanical Engineers, Part I: Journal of Systems and Control Engineering 221, no. 6 (September 1, 2007): 833–43. http://dx.doi.org/10.1243/09596518jsce365.

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A critical component of an advanced gas-cooled reactor station is the graphite core. As a station ages, the graphite bricks that comprise the core can distort and may eventually crack. Since the core cannot be replaced, the core integrity ultimately determines the station life. Monitoring these distortions is usually restricted to the routine outages, which occur every few years, as this is the only time that the reactor core can be accessed by external sensing equipment. This paper presents a monitoring module based on model-based techniques using measurements obtained during the refuelling process. A fault detection and isolation filter based on unknown input observer techniques is developed. The role of this filter is to estimate the friction force produced by the interaction between the wall of the fuel channel and the fuel assembly supporting brushes. This allows an estimate to be made of the shape of the graphite bricks that comprise the core and, therefore, to monitor any distortion on them.

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23

Wallace, C. J., G. M. West, S. D. J. McArthur, and D. Towle. "Distributed Data and Information Fusion for Nuclear Reactor Condition Monitoring." IEEE Transactions on Nuclear Science 59, no. 1 (February 2012): 182–89. http://dx.doi.org/10.1109/tns.2011.2176959.

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24

Hurd, Greg L., and Melvin C. Haun. "Virtual instrumentation applied to monitoring of nuclear reactor refuel process." Laboratory Robotics and Automation 10, no. 2 (1998): 67–69. http://dx.doi.org/10.1002/(sici)1098-2728(1998)10:2<67::aid-lra4>3.0.co;2-v.

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25

Bowden, N. S. "Reactor monitoring using antineutrino detectors." Nuclear Physics B - Proceedings Supplements 217, no. 1 (August 2011): 134–36. http://dx.doi.org/10.1016/j.nuclphysbps.2011.04.085.

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26

Marcillo, Omar E., Monica Maceira, Chengping Chai, Christine Gammans, Riley Hunley, and Chris Young. "The Local Seismoacoustic Wavefield of a Research Nuclear Reactor and Its Response to Reactor Power Level." Seismological Research Letters 92, no. 1 (November 11, 2020): 378–87. http://dx.doi.org/10.1785/0220200139.

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Abstract We describe the seismoacoustic wavefield recorded outdoors but inside the facility fence of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (Tennessee). HFIR is a research nuclear reactor that generates neutrons for scattering, irradiation research, and isotope production. This reactor operates at a nominal power of 85 MW, with a full-power period between 24 and 26 days. This study uses data from a single seismoacoustic station that operated for 60 days and sampled a full operating reactor cycle, that is, full-power operation and end-of-cycle outage. The analysis presented here is based on identifying signals that characterize the steady, that is, full-power operation and end-of-cycle outage, and transitional, that is, start-up and shutdown, states of the reactor. We found that the overall seismoacoustic energy closely follows the main power cycle of the reactor and identified spectral regions excited by specific reactor operational conditions. In particular, we identified a tonal noise sequence with a fundamental frequency around 21.4 Hz and multiple harmonics that emerge as the reactor reaches 90% of nominal power in both seismic and acoustic channels. We also utilized temperature measurements from the monitoring system of the reactor to suggest links between the operation of reactor’s subsystems and seismoacoustic signals. We demonstrate that seismoacoustic monitoring of an industrial facility can identify and track some industrial processes and detect events related to operations that involve energy transport.

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27

Khan, Salah Ud-Din, Zeyad Almutairi, and Meshari Alanazi. "Techno-Economic Assessment of Fuel Cycle Facility of System Integrated Modular Advanced Reactor (SMART)." Sustainability 13, no. 21 (October 26, 2021): 11815. http://dx.doi.org/10.3390/su132111815.

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The economic assessment of advanced nuclear power reactors is very important, specifically during the early stages of concept design. Therefore, a study was performed to calculate the total cost estimation of fuel cycle supply for a system modular advanced reactor (SMART) by using the Generation-IV economic program called G4-ECONS (Generation 4 Excel-based Calculation of Nuclear Systems). In this study, the detailed description of each model and methodology are presented including facility, operations, construction matrix, post-production model, and fuel cycle cost estimation model. Based on these models, six Generation-III+ and Generation-IV nuclear reactors were simulated, namely System 80+ with benchmark data, System 80+ with uranium oxide (UOx) and mixed oxide (MOx) fuel assemblies, fast reactor, PBMR (Pebble Bed Modular Reactor), and PWR (Pressurized Water Reactor), with partially closed and benchmarked cases. The total levelized costs of these reactors were obtained, and it was observed that PBMR showed the lowest cost. The research was extended to work on the SMART reactor to calculate the total levelized fuel cycle cost, capital cost, capital component cost, fraction of capital spent, and sine curve spent pattern. To date, no work is being reported to calculate these parameters for the SMART reactor. It was observed that SMART is the most cost-effective reactor system among other proven and advanced pressurized water-based reactor systems. The main objective of the research is to verify and validate the G4-ECONS model to be used for other innovative nuclear reactors.

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28

Pane, Jupiter Sitorus, Pande Made Udiyani, Muhammad Budi Setiawan, Surip Widodo, and I. Putu Susila. "PRELIMINARY DEVELOPMENT OF RADIONUCLIDES RELEASE OF INDIVIDUAL DOSE CODE PROGRAM FOR RADIATION MONITORING PURPOSES." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 23, no. 3 (September 23, 2021): 91. http://dx.doi.org/10.17146/tdm.2021.23.3.6240.

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Environmental radiation monitoring is one of the important efforts in protecting society and the environment from radiation hazards, both natural and artificial. The presence of three nuclear research reactors and plans to build a nuclear power plant reactor prompted Indonesia to prepare a radiation monitoring system for safety and security (SPRKK). The goal of the study is to provide an appropriate method for developing radiation monitoring system to support the development of nuclear power plant in the near future. For this preliminary study, the author developed a code program using Gaussian distribution model approach for predicting radionuclide release and individual dose acceptancy by human being within 16 wind directions sectors and up to 50 km distance. The model includes estimation of source term from the nuclear installation, release of radionuclides source into air following Gaussian diffusion model, some of the release deposit to the land and entering human being through inhalation, direct external exposure, and resuspension, and predicted its accepted individual dose. This model has been widely used in various code program such as SimPact and PC-Cosyma. For this study, the model will be validated using SimPact code program. The model has been successfully developed with less than 5% deviation. Further study will be done by evaluating the model with real measuring data from research reactor installation and prepare for interfacing with real time radiation data acquisition and monitoring as part of radiation monitoring system during normal and accident condition.

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29

Mitin, V. I. "Technical means of in-reactor monitoring on the VV�R reactor." Soviet Atomic Energy 60, no. 1 (January 1986): 6–11. http://dx.doi.org/10.1007/bf01129830.

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30

Madron, Frantisek, Miloslav Hostalek, and Leo Stepan. "Protection of a Nuclear Reactor Monitoring System against Gross Measurement Errors." International Journal of Nuclear Energy Science and Engineering 5 (2015): 9. http://dx.doi.org/10.14355/ijnese.2015.05.002.

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31

Saedtler, E. "A Multi-Processor System for Vibration Monitoring of Nuclear Reactor Components." IFAC Proceedings Volumes 18, no. 5 (July 1985): 1865–70. http://dx.doi.org/10.1016/s1474-6670(17)60841-3.

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32

Kiss, E., and S. Ranganath. "On-line monitoring to assure structural integrity of nuclear reactor components." International Journal of Pressure Vessels and Piping 34, no. 1-5 (January 1988): 3–15. http://dx.doi.org/10.1016/0308-0161(88)90038-5.

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33

Kuzina, Yu, and A. Sorokin. "FUNDAMENTAL INVESTIGATONS IN THE FIELD OF NUCLEAR POWER FACILITIES THERMOPHYSICS: ACHIEVED RESULTS AND PROBLEMS FOR FURTHER INVESTIGATON." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2020, no. 1 (March 26, 2020): 177–204. http://dx.doi.org/10.55176/2414-1038-2020-1-177-204.

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The results of experimental and theoretical calculations of fundamental research in the field of hydrodynamics, heat transfer, physical chemistry and nuclear power technology cooled by water and liquid metal coolants are analyzed, problems and tasks of further research are formulated. The effects and physical phenomena, laws and characteristics for a wide range of processes occurring in the first and second circuits of reactor facilities, including the flow part, the core, the heating equipment, the means of monitoring and cleaning coolants from impurities as applied to watercooled thermal neutron reactors, fast liquid metal reactors, fusion plants, etc. Particular attention in the field of hydrodynamics and heat transfer is given to studies of the heat transfer crisis in watercooled reactors, hydrodynamics of collector systems, stratification and mixing of jets, vibroacoustics, turbulent transfer in complex channels, heat transfer in the channels and assemblies of fast reactor fuel elements, contact thermal resistance, boiling in large volume and bundles of fuel rods, condensation of liquid metals. In the field of physical chemistry and the technology of liquid metal coolants, the types of impurities and the sources of their entry into the coolants for various nuclear power plants, the characteristics of the mass and heat transfer processes in the circuits and equipment of reactor facilities with liquid metal coolants (sodium, potassium, lithium, lead, bismuth lead), the efficiency of using various purification devices (cold and hot traps) and monitoring the state of impurities in coolants are analyzed.Problem questions and suggestions for further research are formulated. Information is given on the key thermophysical problems of basic research in relation to the development of innovative nuclear energy technologies: water-cooled reactors with supercritical water pressure, high-temperature fast reactors with sodium coolant for hydrogen production, thermonuclear installations, nuclear power plants with liquid-metal space coolants.

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34

Zhang, Liming, Qiao Li, Jingdong Luo, Lin Li, and Yiming Wang. "Rolling Wheel Abrasion Condition Monitoring of Control Rod Drive Mechanism in Nuclear Reactor." Journal of Physics: Conference Series 2186, no. 1 (February 1, 2022): 012005. http://dx.doi.org/10.1088/1742-6596/2186/1/012005.

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Abstract During the operation of in nuclear reactor, the reliability is largely influenced by the changes of working states of control rod drive mechanism. The abrasion of rolling wheel is one of the most serve faults leading to the control failure. To monitor the rolling wheel in the control rod drive mechanism in nuclear reactor, a new recognition method based on complexity of the singular spectrum entropy has been introduced. In this method, the singular spectrum entropy of vibration signal of the system is firstly calculated. Then an index of brain wave information complexity is used to define the singular spectrum entropy complexity. The complexity index is more sensitive to the uncertainty of the signal and it can effectively reflect the intensity of the random shock signal by abrasion which makes it possible to assess the abrasion condition. Through the control rod drive mechanism of whole life test, it is proved that this method can be used in nuclear reactor control rod drive mechanism rolling wheel abrasion condition monitoring with proper accuracy.

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35

Jia, Wei Zhi, Rui Wang, and Yun Zhou. "Nodal Expansion and its Application in AP1000 Nuclear Reactor Core Monitoring System." Applied Mechanics and Materials 448-453 (October 2013): 1907–11. http://dx.doi.org/10.4028/www.scientific.net/amm.448-453.1907.

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As the core monitoring system of AP1000, BEACON always uses a full-core nodal model for core monitoring based on the ANC-NEM nodal model. The theory behind the nodal expansion method is discussed, and the application of the method in BEACON is described. Finally, an ANC-NEM calculation simulation is proposed.

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36

Abramov, A., A. Chepurnov, A. Etenko, M. Gromov, A. Konstantinov, D. Kuznetsov, E. Litvinovich, et al. "iDREAM: industrial Detector of REactor Antineutrinos for Monitoring at Kalinin nuclear power plant." Journal of Instrumentation 17, no. 09 (September 1, 2022): P09001. http://dx.doi.org/10.1088/1748-0221/17/09/p09001.

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Abstract The paper is devoted to the description of the iDREAM detector and its systems. iDREAM is a prototype detector designed to demonstrate the feasibility of antineutrino detectors for remote reactor monitoring and safeguard purposes. Antineutrinos are detected with a 1 ton liquid scintillator via inverse beta decay on protons. In order to suppress cosmic muons, gamma and neutron background, the detector is housed in a dedicated shielding. The detector is installed at the Kalinin nuclear power plant (Russia), 20 m from the 3 GWth reactor core.

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37

Hashemian, H. M. "Predictive maintenance in nuclear power plants through online monitoring." Nuclear and Radiation Safety, no. 4(60) (December 12, 2013): 42–50. http://dx.doi.org/10.32918/nrs.2013.4(60).08.

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The nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automating testing activities. These developments have stimulated great interest in online monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. This paper provides examples of these technologies with particular emphasis on a number of key OLM applications: detecting sensing-line blockages, testing the response time of pressure transmitters, monitoring the calibration of pressure transmitters online, cross-calibrating temperature sensors in situ, assessing equipment condition, and performing predictive maintenance of reactor internals.

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38

Fukunishi, Kohyu, and Satoshi Suzuki. "Real-Time Stability Monitoring Method for Boiling Water Reactor Nuclear Power Plants." Nuclear Technology 78, no. 2 (August 1987): 132–39. http://dx.doi.org/10.13182/nt87-a33991.

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39

Gusarov, Andrei I. "Temperature monitoring of nuclear reactor cores with multiplexed fiber Bragg grating sensors." Optical Engineering 41, no. 6 (June 1, 2002): 1246. http://dx.doi.org/10.1117/1.1475739.

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40

Nabeshima, K., T. Suzudo, T. Ohno, and K. Kudo. "Nuclear reactor monitoring with the combination of neural network and expert system." Mathematics and Computers in Simulation 60, no. 3-5 (September 2002): 233–44. http://dx.doi.org/10.1016/s0378-4754(02)00018-6.

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41

Baliza, Ana Rosa, Amir Zacarias Mesquita, Youssef Morghi, Valéria Emiliana Alcântara e. Alves, Alexandre Melo de Oliveira, Sâmara Gomes Davi, Ângela Moreira Marques dos Santos, and Daniel Artur Pinheiro Palma. "Evaluation of the aging management system for the Triga research nuclear reactor in Brazil / Avaliação do sistema de gerenciamento do envelhecimento do reator nuclear de pesquisa Triga no Brasil." Brazilian Journal of Development 8, no. 4 (April 4, 2022): 23598–607. http://dx.doi.org/10.34117/bjdv8n4-058.

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As most research reactors have over 40 years of operational experience, maintenance, modernization and renovation are increasingly important for safety and operational life extension. This is due to the monitoring and development of techniques to control and mitigate the negative effects of operating conditions on structures, systems and components. Aging management is a strategy of engineering, operation, maintenance and other actions to control, within acceptable limits, the aging degradation of the facility. The first criticality of the IPR-R1 Triga research reactor (Training, Research, Isotopes, Atomics) occurred in 1960 with a maximum thermal power of 30 kW. Therefore, this reactor has been operating for more than 60 years. One of the issues that comes from the long time of the operation is the management of aging. This includes functions and issues related to operation, inspections, design changes, testing, and others. The IPR-R1 reactor is a North American project. So, the requirements of United State Nuclear Regulatory Commission (U.S.NRC) are applicable. This article discusses the International Atomic Energy Agency (IAEA), and U.S.NRC requirements to implement an aging management system for the CDTN IPR-R1 Triga Reactor.

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Gurevich, M. I., O. V. Tel’kovskaya, and D. A. Shkarovskii. "Visualization of models of nuclear reactors for investigating and monitoring reactor behavior in the regular regime." Atomic Energy 104, no. 1 (January 2008): 49–53. http://dx.doi.org/10.1007/s10512-008-0008-8.

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Kim, Young Baik, Felipe P. Vista, Seung Bin Cho, and Kil To Chong. "Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant." Applied Sciences 10, no. 23 (November 24, 2020): 8331. http://dx.doi.org/10.3390/app10238331.

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This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its accuracy was evaluated and proven by comparing the model data with data gathered from tests and plant operations. A conceptual design was proposed through a combined structure that digitalizes only part of the system. The detector signal pre-amplification remains in analog form while the other functions such as reactor power calculation as well as signal conditioning and processing will be digitalized. Simulations showed that the true mean squared voltage (MSV) of the digitalized ENFMS maintained a linear relationship between real and estimated reactor power in the wide range compared to averaged magnitude squared value of analog ENFMS. Extended Kalman Filter (EKF) was also utilized for estimating reactor power and reactor period from measurement signals that are contaminated with gamma ray interaction and electric noise. This study proved that the ENFMS can be successfully digitalized as proposed wherein all functional and performance requirements are satisfied. Simulations results demonstrated that the functions and performance can be improved through the use of digital processing algorithms such as EKF and MSV.

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Abdelrahman, Marwa, Mohamed ElBatanouny, Kenneth Dixon, Michael Serrato, and Paul Ziehl. "Remote Monitoring and Evaluation of Damage at a Decommissioned Nuclear Facility Using Acoustic Emission." Applied Sciences 8, no. 9 (September 14, 2018): 1663. http://dx.doi.org/10.3390/app8091663.

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Reinforced concrete systems used in the construction of nuclear reactor buildings, spent fuel pools, and related nuclear facilities are subject to degradation over time. Corrosion of steel reinforcement and thermal cracking are potential degradation mechanisms that adversely affect durability. Remote monitoring of such degradation can be used to enable informed decision making for facility maintenance operations and projecting remaining service life. Acoustic emission (AE) monitoring has been successfully employed for the detection and evaluation of damage related to cracking and material degradation in laboratory settings. This paper describes the use of AE sensing systems for remote monitoring of active corrosion regions in a decommissioned reactor facility for a period of approximately one year. In parallel, a representative block was cut from a wall at a similar nuclear facility and monitored during an accelerated corrosion test in the laboratory. Electrochemical measurements were recorded periodically during the test to correlate AE activity to quantifiable corrosion measurements. The results of both investigations demonstrate the feasibility of using AE for corrosion damage detection and classification as well as its potential as a remote monitoring technique for structural condition assessment and prognosis of aging structures.

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Grando, Quentin, Léna Lebreton, Vincent Chevalier, Jacques Di Salvo, Stéphane Eymery, Claude Gaillard, Nathalie Monchalin, and Jérôme Guillot. "CABRI test events monitoring through three measurement systems." EPJ Web of Conferences 253 (2021): 04013. http://dx.doi.org/10.1051/epjconf/202125304013.

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The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA). When the thermal-hydraulic conditions representative of a pressurized water nuclear reactor are reached (mostly temperature, pressure and flowrate conditions), a fuel test rod is submitted to a power excursion, triggered by the specific 3He reactivity injection system, in order to simulate a control rod ejection accident. The experiment, managed by IRSN, aims at studying both the fuel and cladding behavior of the test rod placed into the center of the reactor during the power excursion. Several test rods pre-irradiated in pressurized nuclear power plants and with different characteristics (burn up, cladding material, fuel type, Zirconia thickness) are considered for the programs performed in the CABRI reactor. Physical phenomena occurring during the power transient are monitored by various measuring systems designed or operated by IRSN. Each system provides information linked with the different phases of the experiment. Three main measuring systems will be considered in this paper: • The test devices, a sample holder that is also implemented with almost fifty sensors used to monitor the environmental parameters in the test channel such as temperature and pressure, and to control the rod behavior during the test sequence; • The Hodoscope, an online fuel motion measurement system, which aims at analyzing the fuel motion deduced from the detection of fast neutrons emitted by the test rod, with a time step of 1ms during the transient; • The IRIS facility, conceived to perform X-ray radiography and tomography imaging before and after a power transient thanks to a linear electron accelerator, as well as quantitative gamma scanning analyses. During the experimental sequence, different events are recorded. This paper focuses on a cladding failure that occurred during the transient and that can be revealed by the three systems mentioned above. The test device instrumentation allows to determine the timing of the failure and to analyze its consequences in the vicinity of the test rod from a thermal and hydraulic point of view, while the hodoscope measures fuel elongation and relocation during the power excursion. The IRIS facility, then, helps to confirm the failure, its location and its extent. These three systems are complementary and they allow the analysis of the same event from different perspectives. Their combination will ease the interpretation of the events in the next steps for the test results analysis. The study case taken into account in this paper concerns nuclear fuel after three irradiation cycles in a commercial PWR.

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Kostic, Ljiljana. "Reactivity determination in accelerator driven reactors using reactor noise analysis." Nuclear Technology and Radiation Protection 17, no. 1-2 (2002): 19–26. http://dx.doi.org/10.2298/ntrp0202019k.

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Feynman-alpha and Rossi-alpha methods are used in traditional nuclear reactors to determine the subcritical reactivity of a system. The methods are based on the measurement of the mean value, variance and the covariance of detector counts for different measurement times. Such methods attracted renewed attention recently with the advent of the so-called accelerator driven reactors (ADS) proposed some time ago. The ADS systems, intended to be used either in energy generation or transuranium transmutation, will use a subcritical core with a strong spallation source. A spallation source has statistical properties that are different from those traditionally used by radioactive sources. In such reactors the monitoring of the subcritical reactivity is very important, and a statistical method, such as the Feynman-alpha method, is capable of resolving this problem.

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Dubi, C. "Modeling elaborate dead time in reactor monitoring using SDE’s." Annals of Nuclear Energy 173 (August 2022): 109078. http://dx.doi.org/10.1016/j.anucene.2022.109078.

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Mitin, V. I., Yu M. Semchenkov, and A. E. Kalinushkin. "Development of an in-reactor monitoring system for VVER." Atomic Energy 106, no. 5 (May 2009): 355–64. http://dx.doi.org/10.1007/s10512-009-9174-6.

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Memon, Tanveer, Khalid Khan, Abdul Jabbar, and Perveen Akhter. "Assessment of the ambient dose rate around research reactors by thermoluminescence dosimeters." Nuclear Technology and Radiation Protection 25, no. 1 (2010): 41–45. http://dx.doi.org/10.2298/ntrp1001041m.

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Monitoring of radiation levels in and around the nuclear research reactors is essential to safe-guarding life and the environment. Background radiation monitoring at the Pakistan Institute of Nuclear Science & Technology (PINSTECH) has been carried out since the early sixties, before the criticality of the 5 MW Pakistan Research Reactor, so as to confirm the safe operation of PINSTECH nuclear facilities. In the present study, ambient dose rate levels were measured around PINSTECH by using TLD-200 (G-2 cards) installed at 15 different locations over a five year period (1998-2002). The mean dose rates for individual locations in the said period ranged from 0.14 ? 0.01 to 0.19 ? 0.03 ?Sv/h, with a mean value of 0.16 ? 0.03 ?Sv/h. The cu- mulative average annual effective dose equivalent spread over 5 years was 204.4 ? 17 ?Sv. The data were compared with the world and averages in other countries. It was concluded that, from the health hazard point of view, the operation of research reactors and other nuclear facilities at PINSTECH presents no risk to public health.

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Hutton, P. H., and R. J. Kurtz. "Acoustic emission for on-line reactor monitoring: Results of intermediate vessel test monitoring and reactor hot functional testing." Nuclear Engineering and Design 86, no. 1 (April 1985): 3–11. http://dx.doi.org/10.1016/0029-5493(85)90203-1.

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