Relevant bibliographies by topics / Nuclear reactor monitoring

Academic literature on the topic 'Nuclear reactor monitoring'

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Published: 10 December 2022
Last updated: 28 January 2023

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Journal articles on the topic "Nuclear reactor monitoring"

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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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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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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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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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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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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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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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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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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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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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Dissertations / Theses on the topic "Nuclear reactor monitoring"

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Jahn, Gordon James. "Agent-based structural condition monitoring for nuclear reactor cores." Thesis, University of Strathclyde, 2011. http://oleg.lib.strath.ac.uk:80/R/?func=dbin-jump-full&object_id=17400.

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A significant proportion of the UK energy needs are currently serviced by a fleet of ageing nuclear reactors. Ensuring that these reactors are operated safely is the highest priority and the structural health of their cores, that provide channels for control rods and coolant gas, is a key aspect. This thesis focuses on the application of structuralhealth monitoring to the graphite reactor cores used in the UK and presents a specification for the use of structural health monitoring (SHM) techniques already es- tablished in bridge and aircraft monitoring, with data obtained through existing reactor monitoring processes. This approach utilises statistical and clustering techniques on monitoring data that can be acquired during online operation of the plant. The use of existing monitoring processes to complement the established inspection regime for nuclear reactors is a novel contribution from this work. As part of proving the SHM approach, this thesis reports on work undertaken to identify suitable data and numerical limits for the cluster analysis. This analysis considers the data with respect to the stated aim of detectin~ core distortion and demonstrates that the chosen data and values are acceptable and conservative in the context of reactor condition monitoring. An assessment of the SHM solution is presented describing the im- plementation of the SHM approach using a multi-agent system (MAS), IMAPS. This implementation required consideration of using MAS tech- nology for condition monitoring, and the novel contribution of a technique for storing and retrieving historical data in a manner concomitant with both MAS and relational database theory is presented.ij The thesis concludes that condition monitoring is feasible on the graphite cores, and that multi-variate analysis through SHM implemented within a MAS offers a storage and analysis platform that can both handle the data volumes and accommodate further extensions as required.
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Wallace, Christopher John. "Distributed data fusion for condition monitoring of graphite nuclear reactor cores." Thesis, University of Strathclyde, 2013. http://oleg.lib.strath.ac.uk:80/R/?func=dbin-jump-full&object_id=20607.

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Nuclear power stations worldwide are exceeding their originally specified design lives and with only limited construction of new generation underway, there is a desire to continue the operation of existing stations to ensure electricity supply. Continued operation of nuclear power stations with degrading and life-limiting components necessitates increased monitoring and inspection, particularly of the reactor cores, to ensure they are safe to operate. The monitoring of a large number of components and their related data sources is a distributed and time consuming process for the engineer given the lack of infrastructure available for collecting, managing and analysing monitoring data. This thesis describes the issues associated with nuclear Condition Monitoring (CM) and investigates the suitability of a distributed framework utilising intelligent software agents to collect, manage and analyse data autonomously. The application of data fusion techniques is examined to estimate unre corded parameters, provide contextualisation for anomalies in order to quickly identify true faults from explainable anomalies and to extract more detail from existing CM data. A generalised framework is described for nuclear CM of any type of reactor, specifying the required components and capabilites based on the design of a suitable Multi Agent System, including the interaction of the framework with existing CM systems and human users. A high level ontology for nuclear CM is proposed and is emphasised as a crucial aspect of the data management and extendability of the framework to incorporate further data sources and analyses. A prototype system, based on the generalised framework is developed for the case of the Advanced Gas-cooled Reactor, with new and existing CM analyses formalised within intelligent agents. Using real station data and simulated fault data, the prototype system was shown to be capable of performing the existing monitoring tasks considerably faster than a human user while retaining all data and analyses for justification and traceability of decisions based on the analyses.
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ROSSI, ROSA H. P. S. "Utilizacao de redes neurais na monitoracao da potencia do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10895.

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IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Ertiame, A. M. S. "Monitoring and fault diagnosis for Chylla-Haase polymerization reactor." Thesis, Liverpool John Moores University, 2016. http://researchonline.ljmu.ac.uk/5001/.

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The main objective of this research is to develop a fault detection and isolation (FDI) methodologies for Cylla-Haase polymerization reactor, and implement the developed methods to the nonlinear simulation model of the proposed reactor to evaluate the effectiveness of FDI methods. The first part of this research focus of this chapter is to understand the nonlinear dynamic behaviour of the Chylla-Haase polymerization reactor. In this part, the mathematical model of the proposed reactor is described. The Simulink model of the proposed reactor is set up using Simulink/MATLAB. The design of Simulink model is developed based on a set of ordinary differential equations that describe the dynamic behaviour of the proposed polymerization reactor. An independent radial basis function neural networks (RBFNN) are developed and employed here for an on-line diagnosis of actuator and sensor faults. In this research, a robust fault detection and isolation (FDI) scheme is developed for open-loop exothermic semi-batch polymerization reactor described by Chylla-Haase. The independent (RBFNN) is employed here when the system is subjected to system uncertainties and disturbances. Two different techniques to employ RBF neural networks are investigated. Firstly, an independent neural network is used to model the reactor dynamics and generate residuals. Secondly, an additional RBF neural network is developed as a classifier to isolate faults from the generated residuals. In the third part of this research, a robust fault detection and isolation (FDI) scheme is developed to monitor the Chylla-Haase polymerization reactor, when it is under the cascade PI control. This part is really challenging task as the controller output cannot be designed when the reactor is under closed-loop control, and the control action will correct small changes of the states caused by faults. The proposed FDI strategy employed a radial basis function neural network (RBFNN) in an independent mode to model the process dynamics, and using the weighted sum-squared prediction error as the residual. The Recursive Orthogonal Least Squares algorithm (ROLS) is employed to train the model to overcome the training difficulty of the independent mode of the network. Then, another RBFNN is used as a fault classifier to isolate faults from different features involved in the residual vector. In this research, an independent MLP neural network is implemented here to generate residuals for detection task. And another RBF is applied for isolation task performing as a classifier. The fault diagnosis scheme is developed for a Chylla-Haase reactor under open-loop and closed-loop control system. The comparison between these two neural network architectures (MPL and RBF) are shown that RBF configuration trained by (RLS) algorithm have several advantages. The first one is greater efficiency in finding optimal weights for field strength prediction in complex dynamic systems. The RBF configuration is less complex network that results in faster convergence. The training algorithms (RLs and ROLS) that used for training RBFNN in chapter (4) and (5) have proven to be efficient, which results in significant faster computer time in comparison to back-propagation one. Another fault diagnosis (FD) scheme is developed in this research for an exothermic semi-batch polymerization reactor. The scheme includes two parts: the first part is to generate residual using an extended Kalman filter (EKF), and the second part is the decision making to report fault using a standardized hypothesis of statistical tests. The FD simulation results are presented to demonstrate the effectiveness of the proposed method. In the lase section of this research, a robust fault diagnosis scheme for abrupt and incipient faults in nonlinear dynamic system. A general framework is developed for model-based fault detection and diagnosis using on-line approximators and adaptation/learning schemes. In this framework, neural network models constitute an important class of on-line approximators. The changes in the system dynamics due to fault are modelled as nonlinear functions of the state, while the time profile of the fault is assumed to be exponentially developing. The changes in the system dynamics are monitored by an on-line approximation model, which is used for detecting the failures. A systematic procedure for constructing nonlinear estimation algorithm is developed, and a stable learning scheme is derived using Lyapunov theory. Simulation studies are used to illustrate the results and to show the effectiveness of the fault diagnosis methodology. Finally, the success of the proposed fault diagnosis methods illustrates the potential of the application of an independent RBFNN, an independent MLP, an Extended kalman filter and an adaptive nonlinear observer based FD, to chemical reactors.
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Inzerillo, Santo. "Nonlinear estimation for condition monitoring of advanced gas-cooled nuclear reactor cores." Thesis, University of Strathclyde, 2012. http://oleg.lib.strath.ac.uk:80/R/?func=dbin-jump-full&object_id=19546.

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As the Advanced Gas-cooled Reactor (AGR) nuclear power stations are ageing, the nuclear core composed by graphite bricks can distort. The direct measurement of the core condition is costly and time-consuming, hence, alternative methods have been developed to provide the necessary information about the core condition. This thesis presents a model-based technique for condition monitoring of AGRs cores using measurements obtained during routine core refuelling process. It has been demonstrated that Fuel Grab Load Trace (FGLT) data gathered during refuelling operations provides, through the magnitude of its friction component, information relating to the condition of the graphite bricks. Therefore, the condition monitoring of an AGR leads to the estimation of the friction force resulting from the interaction of the fuel assembly and the core channel. To this end the main objective of this work is to investigate estimation techniques that are needed in industrial applications and in particular can be used in the refuelling filtering problem. As a result of this study, a novel LPV estimator and robust estimator have been designed and implemented. A model for the refuelling system was initially developed from the first principles of the process. Then its fuel assembly dynamics subsystem was identified to be used in a model based filtering application. Finally a H robust estimator was employed to estimate the friction force to be used for the core condition analysis.
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Stewart, Christopher L. "Antineutrino-based safeguards for ultra-high burnup fast reactors." Diss., Georgia Institute of Technology, 2016. http://hdl.handle.net/1853/55024.

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Since the first observation of antineutrinos from beta decay of the fission products inside a nuclear reactor in 1956, the design and operating experience of antineutrino detectors near reactors has increased to the point where monitoring the reactor's power level and progression through its burnup cycle has become possible. With the expected increase in world nuclear energy capacity, including the dissemination of reactor technologies to non-nuclear states, the need for safeguards measures which are able to provide continuous, near-real-time information about the state of the core, including its isotopic composition, in a tamper- and spoof-resistant manner is evident. Near-field (~20 m from the core) antineutrino detectors are able to fulfill this demand without perturbing normal reactor operation, without requiring instrumentation which penetrates the reactor vessel, and without displacing other plant structures. Two sodium-cooled long-life fast reactors that are characteristic of next-generation reactors which are attractive for installation in non-nuclear states, one large and one small power rating, have been modeled throughout their reference burnup cycles using MCC-3 and DIF3D/REBUS. Various diversions of fissile material from the core designed to obtain weapons-usable material for the purpose of nuclear proliferation were studied as perturbed core states. The difference in detector event rates between the reference and perturbed states was used to determine the probability that a particular diversionary activity would be apparent before the material could be converted into a weapon. These data indicate which types of diversion antineutrino safeguards are particularly strong against and how the technology might be implemented in current and future international policies concerning nuclear proliferation.
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Neighbour, Gareth Bryan. "Microstructural processes leading to fracture in nuclear graphites." Thesis, University of Bath, 1993. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.332601.

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Berglöf, Carl. "On measurement and monitoring of reactivity in subcritical reactor systems." Doctoral thesis, KTH, Reaktorfysik, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-12483.

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Accelerator-driven systems have been proposed for incineration of transuranic elements from spent nuclear fuel. For safe operation of such facilities, a robust method for reactivity monitoring is required. Experience has shown that the performance of reactivity measurement methods in terms of accuracy and applicability is highly system dependent. Further investigations are needed to increase the knowledge data bank before applying the methods to an industrial facility and to achieve license to operate such a facility. In this thesis, two systems have been subject to investigation of various reactivity measurement methods. Conditions for successful utilization of the methods are presented, based on the experimental experience. In contrast to previous studies in this field, the reactivity has not only been determined, but also monitored based on the so called beam trip methodology which is applicable also to non-zero power systems. The results of this work constitute a part of the knowledge base for the definition of a validated online reactivity monitoring methodology for facilities currently being under development in Europe (XT-ADS and EFIT).
QC 20100621
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FERREIRA, JUNIOR DECIO B. M. "Desenvolvimento de um sistema computacional para monitoracao dos parametros de reatividade e das oscilacoes axiais de xenonio do reator nuclear de Agra 1." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10918.

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IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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MINDA, ELISE. "SENSITIVITY STUDIES ON NONDESTRUCTIVE EVALUATION (NDE) METHODS FOR MONITORING FATIGUE AND THERMAL EMBRITTLEMENT IN AUSTENITIC AND FERRITIC STEEL NUCLEAR REACTOR PLANT (NRP) COMPONENTS." University of Cincinnati / OhioLINK, 2007. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1195611890.

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Books on the topic "Nuclear reactor monitoring"

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Takahashi, Sentaro. Radiation Monitoring and Dose Estimation of the Fukushima Nuclear Accident. Cham: Springer Nature, 2014.

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Damiano, B. Current applications of vibration monitoring and neutron noise analysis: Detection and analysis strutural degradation of reactor vessel internals from operational aging. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

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Office, General Accounting. Nuclear waste: Improvements needed in monitoring contaminants in Hanford soils : report to the chairman, Committee on Governmental Affairs, U.S. Senate. Washington, D.C: GAO, 1992.

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Office, General Accounting. Nuclear waste: Fourth annual report on DOE's nuclear waste program : report to Congress. Washington, D.C: The Office, 1988.

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Office, General Accounting. Nuclear waste: Fourth annual report on DOE's nuclear waste program : report to Congress. Washington, D.C: The Office, 1988.

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Office, General Accounting. Nuclear waste: Institutional relations under the Nuclear Waste Policy Act of 1982 : report to congressional requestors. Washington, D.C: The Office, 1987.

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Office, General Accounting. Nuclear waste: Status of DOE's implementation of the Nuclear Waste Policy Act : report to the Congress. Washington, D.C: GAO, 1987.

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Office, General Accounting. Nuclear waste: Institutional relations under the Nuclear Waste Policy Act of 1982 : report to congressional requestors. Washington, D.C: The Office, 1987.

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Office, General Accounting. Nuclear waste: Institutional relations under the Nuclear Waste Policy Act of 1982 : report to congressional requestors. Washington, D.C: The Office, 1987.

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Office, General Accounting. Nuclear waste: Corps of Engineers' progress in cleaning up 22 nuclear sites : report to the Chairman, Committee on Commerce, House of Representatives. Washington, D.C. (P.O. Box 37050, Washington, D.C. 20013): The Office, 1999.

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Book chapters on the topic "Nuclear reactor monitoring"

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Parker, Michael C., Joseph L. Brittin, and Frank Niziolek. "On-Line Nuclear Power Reactor Accident Monitoring." In Computer Supported Risk Management, 145–61. Dordrecht: Springer Netherlands, 1995. http://dx.doi.org/10.1007/978-94-011-0245-2_9.

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Pázsit, I., N. S. Garis, and P. Lindén. "Application of Neural Networks in Reactor Diagnostics and Monitoring." In Fuzzy Systems and Soft Computing in Nuclear Engineering, 258–84. Heidelberg: Physica-Verlag HD, 2000. http://dx.doi.org/10.1007/978-3-7908-1866-6_12.

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Bennett, Peter, and Torill Karlsen. "11 In-core corrosion monitoring in the Halden test reactor." In Corrosion monitoring in nuclear systems: research and applications, 171–93. Boca Raton London New York: CRC Press, 2017. http://dx.doi.org/10.1201/9781315140391-12.

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Jester, William A., T. T. Tseng, and B. S. Lee. "Radioiodine Monitoring of Nuclear Power Plant Airborne Emissions Under Accident Conditions." In Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry, 915–22. Dordrecht: Springer Netherlands, 1992. http://dx.doi.org/10.1007/978-94-011-2781-3_105.

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Rui, Han, and Chen Shu-ming. "Sodium-Cooled Fast Breed Reactor Fuel Failure Detection Based on Cover Gas Monitoring." In Proceedings of The 20th Pacific Basin Nuclear Conference, 881–92. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2314-9_79.

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Molander, Anders, Katarina Pein, Anna-Lena Forsgren, and Gösta Karlberg. "Corrosion Potential Monitoring in Swedish BWRS on Hydrogen Water Chemistry." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 453–60. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch46.

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Upadhyaya, Belle R., Jamie B. Coble, and J. Wesley Hines. "Equipment and Process Condition Monitoring for Asset Management in Small Modular Nuclear Reactors." In Proceedings of the 10th World Congress on Engineering Asset Management (WCEAM 2015), 629–36. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-27064-7_63.

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Cassagne, Thierry, Didier Caron, Jacques Daret, Alain Proust, Henri Mazille, Guy Turluer, and Dominique Boulanger. "Initial Results on the Stress Corrosion Cracking Monitoring of Alloy 600 in High Temperature Water Using Acoustic Emission." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 225–33. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch23.

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Bregani, F., and R. Rizzi. "Paper 70. Corrosion monitoring in decontamination processes." In WATER CHEMISTRY OF NUCLEAR REACTOR SYSTEMS 4, 225–26. Thomas Telford Publishing, 1986. http://dx.doi.org/10.1680/wconrs4v1.03705.0052.

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Yucheng, Lu, and Zhang Mengqin. "Corrosion Monitoring in Chemical Cleaning of Steam Generator." In Water chemistry of nuclear reactor systems 8, 2: 527–529. Thomas Telford Publishing, 2001. http://dx.doi.org/10.1680/wconrs8v2.29583.0027.

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Conference papers on the topic "Nuclear reactor monitoring"

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BOLDYREV, GENNADII, and ALEKSANDR ZHIVAEV. "Dynamic Monitoring of Nuclear Reactor Protection Shell." In Structural Health Monitoring 2015. Destech Publications, 2015. http://dx.doi.org/10.12783/shm2015/41.

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Brumovsky, Milan, and Milos Kytka. "Monitoring Degradation in Nuclear Reactors." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-45511.

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Nuclear reactor materials are affected by many stressors during their operation that result either from the nuclear reactions in the reactor core or by operation conditions (temperature, pressure) and water environment. Generally, several different methods of monitoring damage in reactor materials are applied, depending on their type, design and conditions: - Destructive, usually represent by surveillance specimens, - Semi-destructive, usually performed by cutting small specimens from component surface, e.g. for small punch tests, - Non-destructive, representing by non-destructive inspection methods applied during in-service inspections, like traditional ultrasonics, optical, dye-penetrant, eddy current etc. and also some new like automated ball indentation, thermoelectric power measurements etc. The paper summarizes the possibility of application of these methods on main reactor components and shows some typical results and problems.
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Giraud, A., and J. Veau. "Full autonomous monitoring tools inside nuclear reactor building." In 2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA). IEEE, 2009. http://dx.doi.org/10.1109/animma.2009.5503710.

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Walsh, Timothy, Mark Chen, Wilkins Aquino, Greg banyay, Michael Zavlanos, and Kavinayan Sivakumar. "Autonomous Structural Health Monitoring For Nuclear Reactor Internals." In Proposed for presentation at the 2nd Annual International Conference on AI, ML, and other Innovative Technologies in the Nuclear Industry (CAIMIN 2021) held November 29-December 1, 2021 in virtual, US. US DOE, 2021. http://dx.doi.org/10.2172/1897696.

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Vijayakumaran, P. M., C. P. Nagaraj, C. Paramasivan Pillai, R. Ramakrishnan, and M. Sivaramakrishna. "Nuclear Instrumentation Systems in Prototype Fast Breeder Reactor." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49354.

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The nuclear instrumentation systems of the Prototype Fast Breeder Reactor (PFBR) primarily comprise of global Neutron Flux Monitoring, Failed Fuel Detection & Location, Radiation Monitoring and Post-Accident Monitoring. High temperature fission chambers are provided at in-vessel locations for monitoring neutron flux. Failed fuel detection and location is by monitoring the cover gas for fission gases and primary sodium for delayed neutrons. Signals of the core monitoring detectors are used to initiate SCRAM to protect the reactor from various postulated initiating events. Radiation levels in all potentially radioactive areas are monitored to act as an early warning system to keep the release of radioactivity to the environment and exposure to personnel well below the permissible limits. Fission Chambers and Gamma Ionisation Chambers are located in the reactor vault concrete for monitoring the neutron flux and gamma radiation levels during and after an accident.
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Molnar, Jozef, Marek Pecka, and Jaroslav Kment. "SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66867.

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During the years 1970–80’ in the satellite countries of the former Soviet Union more than 24 new reactor builds were started. In the former Czechoslovakia, the new builds were realized with a high degree of input from the local engineers and the local industry. This territory up to today has an indigenous nuclear industry, machinery and nuclear engineering background. Starting with the year 1972, on the territory of Czechoslovakia (now on the territory of the Czech and Slovak Republic) 12 new units of the VVER-440 type of reactors were started to build. Nowadays the 2 oldest units were already shutdown in Slovakia, 4+4 units are still operating in both countries, and 2 units of VVER-440 model V213 are still under construction in Slovakia. The reactors designed lifetime in original configuration are 30 years. During these units’ operation period, wide range of modifications and upgrades were performed to strengthen the nuclear safety and the reactors operability. In 2015/16, activities related to the unit operation licenses extension were carried out in both of countries. In scope of strengthening the reactor’s core monitoring and surveillance, at Dukovany NPP (CZ, 1998) and at Bohunice NPP (SK, 2001) the original Russian VK3 computation system was completely replaced with an alternative advanced Core Monitoring and Surveillance System (CMS) SCORPIO-VVER. In Hungary, a locally developed “Verona”, and on the units under construction in Slovakia the Russian “Kruiz” CMS is used. Nowadays the SCORPIO-VVER CMS presents a nuclear fuel type and fuel vendor independent, advanced computer based reactor core monitoring system with an open and flexible framework, including the latest achievements in the fields of N/F and T/H for reliable and safe reactor operation with high efficiency of fuel cycle. The system’s framework governing the know-how and knowledge of 5 European institutes with proven experiences with reactor operation, fuel pattern and fuel campaign design and with utilizing the existing unit’s project reserves to increase the reactor operation and fuel campaign efficiency. Since the first installation the SCORPIO-VVER CMS system has a remarkable operating history and experience. More than 18 years of experiences at 6 units of VVER-440 type of reactors in two different countries helps to put the system to a very high level of usability and reliability. Even if the SCORPIO-VVER is installed only on VVER-440 reactors, it could be adapted to the needs of other VVER type of reactors and to needs of education and training centers too.
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Askari, Vahid. "Automated Operation With Redundant Ultrasonic Reactor Water Level Monitoring System." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75162.

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The proposed ultrasonic Reactor water Level Monitoring system is intended for monitoring water level in the hot leg of a nuclear reactor during Operation at Reduced Inventory (ORI) with the core in place as may be needed for certain maintenance activities. Since the existing fuel bundles continue the production of heat thorough the decay process, it is critical to maintain a certain water flow rate through the reactor. The Residual Heat Removal System (RHRS) handles this task during the reactor shutdown. The free water surface during ORI subjects the RHRS to the risk of air intake. Such an event would trigger a set of emergency procedures for priming the RHRS and bringing it back online. Some of the possible outcomes of such an event are: extension of outage, handling of the extra regulatory reporting tasks, potential requirements for extra testing after system recovery, possible damage to RHR pump, boiling of reactor water, generation of airborne contamination, and fuel damage. Another risk during ORI is reactor overflow. The major immediate concern is the safety of personnel in case of accidental overflow. This event could result in contamination and the related outage delays. The previously existing systems have always had problems with transducer reliability. This has lead to the need for removal and re-installation of their transducers from outage to outage. However, the proposed system uses a redundant design with permanently mounted transducers. The system uses advanced digital signal processing techniques to determine the water level.
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Jung, Byung Ryul, In Ho Song, Jung Hoon Kim, Byung Jin Lee, Se Jin Baik, Joon Sung Kim, Jong Sun Lee, and Teuk Ki Choe. "An Application of Main Steam Flow-Based Power Monitoring to OPR1000 Plants." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75642.

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It is extremely important in managing nuclear power plants to accurately confirm the thermal power of reactor for controlling and monitoring the plant power output. For pressurized water reactors (PWRs), feedwater flowrates have been typically used for mass and energy balance calculations to confirm the reactor thermal power. The feedwater flowrates are calculated from pressure drop measurements across venturis in plant feedwater systems. There have been so far many reports on the fouling of venturi, which has lead to erroneous high pressure drop measurements. This gives high mass flowrates, leading to high calculated reactor thermal power. The high calculated thermal power causes plant operators to reduce the power output to comply with the licensed operating power level. This causes losses in plant electrical output, typically about 2 ∼ 3% of the plant rating. One method to overcome the overestimation of reactor power due to high calculated feedwater flowrates due to venturi fouling is using steam flow measurements in reactor thermal power calculations. Plant operating experiences have shown that steam flows are a closer indicator of plant power. In addition they are known to show little fouling problem. A new power calculation methodology based on steam flow measurements is proposed herein for mass and energy balance calculations of reactor thermal power. A mathematical mass flowrate equation is developed for measured steam flows in a similar way to feedwater flows. The steam flow correction factors are determined from the operating data gained at the beginning of operation cycle. This is a way to calibrating steam flow measurements to feedwater flow indications to allow for the calorimetric heat balance to be based on steam flow rather than feedwater flow. Routine calibration testing procedure is developed to determine discharge coefficients for each operation cycle. The results of application to the Optimized Power Reactor 1000 (OPR1000) plants show good performance in plant power monitoring.
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Ecker, Lynne, Jacopo Saccheri, Biays Bowerman, James Ablett, Laurence Milian, Jay Adams, Hans Ludwig, and Michael Todosow. "An Infiltration Manufacturing Process for Nuclear Fuels." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58204.

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The Infiltrated Kernel Nuclear Fuel (IKNF) process deposits nuclear fuel into the naturally occurring porosity in graphite. IKNF consists of infiltrating uranyl nitrate dissolved in an organic solvent into the graphite and then heat-treating the sample at low (<300°C) temperatures to remove the solvent and convert the uranyl nitrate to UO2. Complete conversion to UC2 can then be accomplished by heating to temperatures higher than 3000°C. IKNF is extremely flexible: it is appropriate for very high temperature applications and heating the infiltrated product to intermediate temperatures (higher than 900°C) produces nuclear fuel with a range of chemistries in the U-C-O system (similar to the current US TRISO fuel). It is probable that the process can also be used to produce fuel containing transuranics. It is believed that IKNF will be less expensive, more robust and more suitable for on-line quality monitoring than current fuel fabrication method. Graphite infiltration involves a few, easily measurable and controllable variables. It is reproducible and predictable.
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Suter, J. D., P. Ramuhalli, J. S. McCloy, K. Xu, S. Hu, Y. Li, W. Jiang, D. J. Edwards, A. L. Schemer-Kohrn, and B. R. Johnson. "Meso-scale magnetic signatures for nuclear reactor steel irradiation embrittlement monitoring." In 41ST ANNUAL REVIEW OF PROGRESS IN QUANTITATIVE NONDESTRUCTIVE EVALUATION: Volume 34. AIP Publishing LLC, 2015. http://dx.doi.org/10.1063/1.4914765.

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Reports on the topic "Nuclear reactor monitoring"

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Hoffheins, B. S., T. E. McKnight, R. J. Lauf, R. R. Smith, and R. E. James. Evaluation of a hydrogen sensor for nuclear reactor containment monitoring. Office of Scientific and Technical Information (OSTI), February 1997. http://dx.doi.org/10.2172/486067.

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Thomas Blue and Don Miller. Nuclear Reactor Power Monitoring Using Silicon Carbide Semiconductor Radiation Detectors. Office of Scientific and Technical Information (OSTI), June 2008. http://dx.doi.org/10.2172/934787.

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Rajadhyaksha, Aditi, Emily Casleton, and Geoffrey Fairchild. Monitoring Nuclear Reactor and Reprocessing Facility Operations Externally using Radiation Detection. Office of Scientific and Technical Information (OSTI), August 2018. http://dx.doi.org/10.2172/1463591.

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Reyna, D. E., and R. W. McKeown. A comparison of the performance of compact neutrino detector designs for nuclear reactor safeguards and monitoring. Office of Scientific and Technical Information (OSTI), October 2006. http://dx.doi.org/10.2172/924686.

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Gribok, Andrei. Light Water Reactor Sustainability Program Potential to Extend the Range of Established Online Monitoring Technologies, Such as Guided Waves in Nuclear Power Plant Systems. Office of Scientific and Technical Information (OSTI), September 2017. http://dx.doi.org/10.2172/1408772.

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Chen, Shikui, Yongjia Wu, Shaoxu Xian, Jackson Klein, Lei Zuo, Thanh Tuong Pham, Sujan Yenuganti, et al. Self-powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors. Office of Scientific and Technical Information (OSTI), March 2019. http://dx.doi.org/10.2172/1505496.

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Fernando, P. U. Ashvin Iresh, Gilbert Kosgei, Matthew Glasscott, Garrett George, Erik Alberts, and Lee Moores. Boronic acid functionalized ferrocene derivatives towards fluoride sensing. Engineer Research and Development Center (U.S.), July 2022. http://dx.doi.org/10.21079/11681/44762.

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In this technical report (TR), a robust, readily synthesized molecule with a ferrocene core appended with one or two boronic acid moieties was designed, synthesized, and used toward F- (free fluoride) detection. Through Lewis acid-base interactions, the boronic acid derivatives are capable of binding with F- in an aqueous solution via ligand exchange reaction and is specific to fluoride ion. Fluoride binding to ferrocene causes significant changes in fluorescence or electrochemical responses that can be monitored with field-portable instrumentation at concentrations below the WHO recommended limit. The F- binding interaction was further monitored via proton nuclear magnetic resonance spectroscopy (1H-NMR). In addition, fluorescent spectroscopy of the boronic acid moiety and electrochemical monitoring of the ferrocene moiety will allow detection and estimation of F- concentration precisely in a solution matrix. The current work shows lower detection limit (LOD) of ~15 μM (285 μg/L) which is below the WHO standards. Preliminary computational calculations showed the boronic acid moieties attached to the ferrocene core interacted with the fluoride ion. Also, the ionization diagrams indicate the amides and the boronic acid groups can be ionized forming strong ionic interactions with fluoride ions in addition to hydrogen bonding interactions.
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