Bibliografías temáticas / Windscale Nuclear Power Station

Literatura académica sobre el tema "Windscale Nuclear Power Station"

Autor: Grafiati

Publicado: 26 de julio de 2024

Última modificación: 28 de julio de 2024

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Artículos de revistas sobre el tema "Windscale Nuclear Power Station"

Juraku, Kohta. "Safety of Nuclear Power Station". Journal of the Atomic Energy Society of Japan 61, n.º 3 (2019): 233–36. http://dx.doi.org/10.3327/jaesjb.61.3_233.

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EGASHIRA, Tadahiko. "Decommissioning of nuclear power station." Doboku Gakkai Ronbunshu, n.º 355 (1985): 174–79. http://dx.doi.org/10.2208/jscej.1985.355_174.

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Daniels, J. R., M. M. R. Williams y M. D. Eaton. "Transient analysis of the 1970 Windscale nuclear criticality incident". Progress in Nuclear Energy 170 (mayo de 2024): 105095. http://dx.doi.org/10.1016/j.pnucene.2024.105095.

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Chan, Yea-Kuang y Yu-Ching Tsai. "Power uprate operation at Chinshan Nuclear Power Station". Nuclear Engineering and Design 343 (marzo de 2019): 96–102. http://dx.doi.org/10.1016/j.nucengdes.2019.01.001.

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ITAKURA, Tetsuro. "Radiation Protection in Nuclear Power Station". Japanese Journal of Health Physics 30, n.º 2 (1995): 107–9. http://dx.doi.org/10.5453/jhps.30.107.

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Daniels, J. R., M. M. R. Williams y M. D. Eaton. "Steady-state analysis of the 1970 Windscale nuclear criticality incident". Progress in Nuclear Energy 169 (abril de 2024): 105046. http://dx.doi.org/10.1016/j.pnucene.2023.105046.

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Wang, Yu Lan. "Safety Performance Evaluation of Nuclear Power Station Containment". Applied Mechanics and Materials 672-674 (octubre de 2014): 418–21. http://dx.doi.org/10.4028/www.scientific.net/amm.672-674.418.

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Nuclear energy as an economical, safe and clean energy is being increasingly concerned, and nuclear power stations have also been widely built in the world. However, because of the impact from nuclear events, the safety of nuclear power station has been suspected by the public. First, the development situation of the nuclear power station in the world is described. Then the nuclear power station containment is introduced. Meanwhile, the safety performance of nuclear power station containment under external events are analyzed. Some advices on guaranteeing the security work of nuclear power station containment are given.

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Pope, Daniel y Henry F. Bedford. "Seabrook Station: Citizen Politics and Nuclear Power." Journal of American History 79, n.º 4 (marzo de 1993): 1690. http://dx.doi.org/10.2307/2080358.

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Skipp, B. O. "Faults near Hinkley Point Nuclear Power Station". Quarterly Journal of Engineering Geology and Hydrogeology 21, n.º 2 (mayo de 1988): 111. http://dx.doi.org/10.1144/gsl.qjeg.1988.021.02.01.

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KERSHAW, PJ, DC WEATHERSEED y J. POLLIN. "TORNESS NUCLEAR POWER STATION: CIVIL ENGINEERING CONSTRUCTION." Proceedings of the Institution of Civil Engineers 78, n.º 5 (octubre de 1985): 1139–63. http://dx.doi.org/10.1680/iicep.1985.921.

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Tesis sobre el tema "Windscale Nuclear Power Station"

Boyes, Haydn. "Sensitivity analysis of the secondary heat balance at Koeberg Nuclear Power Station". Master's thesis, Faculty of Engineering and the Built Environment, 2021. http://hdl.handle.net/11427/33686.

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At Koeberg Nuclear Power Station, the reactor thermal power limit is one of the most important quantities specified in the operating licence, which is issued to Eskom by the National Nuclear Regulator (NNR). The reactor thermal power is measured using different methodologies, with the most important being the Secondary Heat Balance (SHB) test which has been programmed within the central Koeberg computer and data processing system (KIT). Improved accuracy in the SHB will result in a more accurate representation of the thermal power generated in the core. The input variables have a significant role to play in determining the accuracy of the measured power. The main aim of this thesis is to evaluate the sensitivity of the SHB to the changes in all input variables that are important in the determination of the reactor power. The guidance provided by the Electric Power Research institute (EPRI) is used to determine the sensitivity. To aid with the analysis, the SHB test was duplicated using alternate software. Microsoft Excel VBA and Python were used. This allowed the inputs to be altered so that the sensitivity can be determined. The new inputs included the uncertainties and errors of the instrumentation and measurement systems. The results of these alternate programmes were compared with the official SHB programme. At any power station, thermal efficiency is essential to ensure that the power station can deliver the maximum output power while operating as efficiently as possible. Electricity utilities assign performance criteria to all their stations. At Koeberg, the thermal performance programme is developed to optimize the plant steam cycle performance and focusses on the turbine system. This thesis evaluates the thermal performance programme and turbine performance. The Primary Heat Balance (PHB) test also measures reactor power but uses instrumentation within the reactor core. Due to its location inside the reactor coolant system, the instrumentation used to calculate the PHB is subject to large temperature fluctuations and therefore has an impact on its reliability. To quantify the effects of these fluctuations, the sensitivity of the PHB was determined. The same principle, which was used for the SHB sensitivity analysis, was applied to the PHB. The impact of each instrument on the PHB test result was analysed using MS Excel. The use of the software could be useful in troubleshooting defects in the instrumentation. A sample of previously authorised tests and associated data were used in this thesis. The data for these tests are available from the Koeberg central computer and data processing system.

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Dinoko, Tshepo Samuel. "Modeling of the dispersion of radionuclides around a nuclear power station". Thesis, University of the Western Cape, 2009. http://etd.uwc.ac.za/index.php?module=etd&action=viewtitle&id=gen8Srv25Nme4_3451_1360933219.

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Nuclear reactors release small amounts of radioactivity during their normal operations. The most common method of calculating the dose to the public that results from such releases uses Gaussian Plume models. We are investigating these methods using CAP88-PC, a computer code developed for the Environmental Protection Agency (EPA) in the USA that calculates the concentration of radionuclides released from a stack using Pasquill stability classification. A buoyant or momentum driven part is also included. The uptake of the released radionuclide by plants, animals and humans, directly and indirectly, is then calculated to obtain the doses to the public. This method is well established but is known to suffer from many approximations and does not give answers that are accurate to be better than 50% in many cases. More accurate, though much more computer-intensive methods have been developed to calculate the movement of gases
using fluid dynamic models. Such a model, using the code FLUENT can model complex terrains and will also be investigated in this work. This work is a preliminary study to compare the results of the traditional Gaussian plume model and a fluid dynamic model for a simplified case. The results indicate that Computational Fluid Dynamics calculations give qualitatively similar results with the possibility of including much more effects than the simple Gaussian plume model.

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程明錦 y Ming-kam Eric Ching. "A regional atmospheric dispersion model for Daya Bay Nuclear Power Station". Thesis, The University of Hong Kong (Pokfulam, Hong Kong), 1990. http://hub.hku.hk/bib/B31209634.

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Rylands, Naasef. "Condition monitoring of induction motors in the nuclear power station environment". Master's thesis, University of Cape Town, 2018. http://hdl.handle.net/11427/29686.

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The induction motor is a highly utilised electrical machine in industry, with the nuclear industry being no exception. A typical nuclear power station usually contains more than 1000 motors, where they are used in safety and non-safety application. The efficient and fault-free operation of this machine is critical to the safe and economical operation of any plant, including nuclear power stations. A comprehensive literature review was conducted that covered the functioning of the induction machine, its common faults and methods of detecting these faults. The Condition Based Maintenance framework was introduced in which condition monitoring of induction machines is an essential component. The main condition monitoring methods were explained with the main focus being on Motor Current Signature Analysis (MCSA) and the various methods associated with it. Three analysis methods were selected for further study, namely, Current Signature Analysis, Instantaneous Power Signature Analysis (IPSA) and Motor Square Current Signature Analysis (MSCSA). Essentially, the methodology used in this dissertation was to study the three common motor faults (bearings, stator and rotor cage) in isolation and compare the results to that of the healthy motor of the same type. The test loads as well as fault severity were varied where possible to investigate its effect on the fault detection scheme. The data was processed using an FFT based algorithm programed in MATLAB. The results of the study of the three spectral analysis techniques showed that no single technique is able to detect motor faults under all tested circumstances. The MCSA technique proved the most capable of the three techniques as it was able to detect faults under most conditions, but generally suffered poor results in inverter driven motor applications. The IPSA and MSCSA techniques performed selectively when compared to MCSA and were relatively successful when detecting the mechanical faults. The fact that the former techniques produce results at unique points in the spectrum would suggest that they are more suitable for verifying results. As part of a comprehensive condition monitoring scheme, as required by a large population of the motors on a nuclear power station, the three techniques presented in this study could readily be incorporated into the Condition Based Maintenance framework where the strengths of each could be exploited.

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Ching, Ming-kam Eric. "A regional atmospheric dispersion model for Daya Bay Nuclear Power Station /". [Hong Kong] : University of Hong Kong, 1990. http://sunzi.lib.hku.hk/hkuto/record.jsp?B12993104.

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Simons, Rowena Chrystal. "An exploratory analysis of quality management audit findings at a nuclear power station". Thesis, Cape Peninsula University of Technology, 2016. http://hdl.handle.net/20.500.11838/2382.

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Thesis (MTech (Quality))--Cape Peninsula University of Technology, 2016.
The quality assurance role is an essential function in high risk industries such as the nuclear power industry where process failures can potentially have catastrophic results. As part of mitigating the risk inherent in such industries, the need for reliable quality assurance cannot be over-emphasised. Underpinning a reliable quality assurance function, lies the need for effective identification of risk; as well as effective decision making processes by competent auditors. A nuclear quality assurance (QA) department has noted an increase in the variability of its audit outcomes, which has resulted in the value of the audit process being questioned by various stakeholders. The research endeavoured to: explore and describe the practice amongst auditors when rating audit findings; potentially identify reasons for inconsistencies amongst auditors when rating findings; and provide recommendations to improve both the consistency amongst auditors when rating audit finding and the overall performance of the audit process. An exploratory study using the Delphi technique was adopted to enable multiple iterations of qualitative and quantitative data collection and analysis, mimicking elements of a sequential exploratory strategy.

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Leung, Wing-mo. "Age dependency of the radiological impact of the daya bay nuclear power station on the local population /". [Hong Kong] : University of Hong Kong, 1994. http://sunzi.lib.hku.hk/hkuto/record.jsp?B13597292.

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Bezuidenhout, Jandré Albert. "Signature analysis of the primary components of the Koeberg nuclear power station / J.A. Bezuidenhout". Thesis, North-West University, 2010. http://hdl.handle.net/10394/4387.

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In line with its commitment to safe nuclear power generation, the Koeberg Nuclear Power Station (KNPS) replaced the outdated vibration monitoring system with a modern on-line vibration monitoring system. This will allow plant personnel to monitor components on a continuous basis which will provide faster response time in the scenario of excessive vibrations of the primary components. This study focuses on the analysis of the vibration of the primary components of the KNPS by analysing the frequency spectra of the vibration signals of the primary components and comparing these to reference signatures obtained during similar operating conditions. The condition of the vibration sensors will also be evaluated. In order to obtain a deeper understanding of the vibration behaviour and hence vibration signatures of the KNPS primary reactor components, a simplified mathematical model of the primary components is developed, based on the system of elasto-dynamic equations. The equations are solved numerically and used to simulate the KNPS vibration monitoring system. The mechanical system is modelled. Time series are generated and Fast Fourier Transforms (FFT) are calculated to simulate the new KNPS monitoring system. In the simulation mechanical degradation of the primary components as well as sensor degradation is simulated. The purpose of this study is to indicate whether mechanical degradation has occurred in the primary components of the plant and to validate the vibration signals. At the same time the study aims to lay a foundation for future monitoring and interpretation of vibration signatures by simulating the vibration and the monitoring signals. It was found that the primary components had not been affected by mechanical degradation as no deviations in resonances were detected in the frequency signatures. A small number of vibration sensors were found to have deteriorated; hence replacement / maintenance was proposed. The mechanical model and the simulation of the monitoring signals proved to be useful to understand and interpret the vibration of the KNPS primary components.
Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2011.

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Oudet, Alexandre. "Design and optimization of the HVAC system for a nuclear power plant demineralization station". Thesis, KTH, Energiteknik, 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-192184.

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Avstängda kärnkraftverk berövar många människor av elektricitet och det skulle ha en negativ inverkan både på företagets framtoning och mänskliga aktiviteter. På grund av detta behöver tillgängligheten av utrustningen i alla byggnaderna som kärnkraftverken består ses till. HVAC-system (Heating, Ventilation and Air Conditioning) spelar en viktig roll när det gäller tillgänglighet av utrustning eftersom dessa system ser till pålitligheten är på topp genom att anpassade omgivningsförhållanden till utrustningen. Att designa ventilationssystemet rätt är därför mycket viktigt och måste göras noggrant. Denna rapport introducerar metodologin för att designa och optimera ett ventilationssystem för en av byggnaderna i ett kärnkraftverk. Utöver detta utvecklas och beskrivs en metodologi för att designa ett rökkontrollssystem för en byggnad som ingår i kärnkraftverket. Dessa metodologier har implementerats för en byggnad i en demineraliseringsstation, Hinkley Point C project.
During nuclear power plants shutdown many people could be deprived of electricity and it would have a negative impact both on the company’s image and on people activities. As a consequence, availability of equipments in the different buildings which compose the power plant needs to be assured. HVAC system (Heating, Ventilation and Air Conditioning) plays an important role on the reliability of these equipments as it makes sure that ambient conditions in the buildings fit the operating temperature range of the equipments. Consequently sizing a ventilation system is really important and it needs to be carried out seriously. This paper introduces the methodology to size and optimize a ventilation system for nuclear power plants’ building. This paper also develops the methodology used to size a smoke control system in a nuclear related building. Direct application of this methodology has been realised for a specific building which is the demineralization station of Hinkley Point C project.

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Gumede, Nomfusi Leticia. "An investigation on the impact of procurement quality management in a nuclear power station". Thesis, Cape Peninsula University of Technology, 2011. http://hdl.handle.net/20.500.11838/2221.

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Thesis (MTech (Quality))--Cape Peninsula University of Technology, 2011.
This research project in Procurement Quality Engineering was conducted at a Nuclear Power Generation Company in the Western Cape, South Africa. During the past decade, quality management has become increasingly recognised as highly desirable for all organisations at all levels. All organisations, to varied degrees, can benefit from the application of quality management skills in some parts of their daily operations. The research project will investigate the impact or effect of late deliveries of spares on the operational cost of the organisation. The organisation is not aware what impact the delivery of spares has on operating costs. Against the above background, the problem to be researched within the ambit of this dissertation reads as follows: "Poor product and / or service delivery from Vendors and / or Suppliers have an adverse impact on the output of the Procurement Quality Department" .The primary research objectives of this study are the following: ~ To emphasise the importance of quality within the supply chain. ~ To investigate the impact of non-conforming items delivered to a Nuclear Power Plant. ~ To determine measures which can be put in place to improve communication between suppliers, vendors, buyers and procurement quality engineering. ~ To determine or investigate the cost of poor quality in the organisation. ~ To improve the quality of goods and services through the application of a quality management system within the supply chain. The research method used in this research project involved both qualitative and quantitative research processes. Questionnaires and statistical techniques were used to analyse the data, and to draw conclusions and recommend possible areas for improvement. The research methodology falls within the ambit of a case study.

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Libros sobre el tema "Windscale Nuclear Power Station"

Zanobetti, D. Power station simulators. Amsterdam: Elsevier, 1989.

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Society, British Nuclear Energy, ed. Nuclear power station project management. London: British Nuclear Energy Society, 1989.

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Electric, Nuclear, ed. Trawsfynydd Nuclear Power Station: Emergency handbook. [s.l.]: Nuclear Electric, 1991.

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PLC, Magnox Electric, ed. Trawsfynydd Nuclear Power Station: Environmental statement. Berkeley: Magnox Electric PLC, 1998.

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Simon, Fullalove y Institution of Civil Engineers (Great Britain), eds. Sizewell B power station. London: Published for the Institution of Civil Engineers by Thomas Telford Services, 1995.

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Arnold, Lorna. Windscale 1957: Anatomy of a nuclear accident. Basingstoke: Macmillan Academic and Professional, 1992.

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Bedford, Henry F. Seabrook Station: Citizen politics and nuclear power. Amherst: University of Massachusetts Press, 1990.

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United States. National Aeronautics and Space Administration., ed. Tethered nuclear power for the space station. [Washington, DC]: National Aeronautics and Space Administration, 1985.

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Great Britain. Ministry of Agriculture, Fisheries and Food. Eastern Region. Accident emergency plan for Bradwell nuclear power station. Cambridge: MAFF, 1990.

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A, Eide S., Grady Anne-Marie, Idaho National Laboratory. Risk, Reliability, and NRC Programs Dept. y U.S. Nuclear Regulatory Commission. Division of Risk Analysis and Applications., eds. Reevaluation of station blackout risk at nuclear power plants. Washington, DC: U.S. Nuclear Regulatory Commission, 2005.

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Capítulos de libros sobre el tema "Windscale Nuclear Power Station"

Ishikawa, Michio. "Three Mile Island Nuclear Power Station Accident". En A Study of the Fukushima Daiichi Nuclear Accident Process, 3–33. Tokyo: Springer Japan, 2015. http://dx.doi.org/10.1007/978-4-431-55543-8_1.

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Jervis, M. W. "Models and Simulation in Nuclear Power Station Design and Operation". En Advances in Nuclear Science and Technology, 77–115. Boston, MA: Springer US, 1986. http://dx.doi.org/10.1007/978-1-4613-2183-5_2.

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Holt, G. y D. L. Brown. "Large Transport and Disposal Packages for Nuclear Power Station Decommissioning Waste". En Transportation for the Nuclear Industry, 157–68. New York, NY: Springer US, 1989. http://dx.doi.org/10.1007/978-1-4757-0046-6_16.

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Bertini, R., C. D’Anna, A. Ceccolini, G. Cuttica y A. Linari. "Transport of Spent Fuel from Garigliano Power Station to an AFR Repository". En Transportation for the Nuclear Industry, 321–33. New York, NY: Springer US, 1989. http://dx.doi.org/10.1007/978-1-4757-0046-6_32.

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Tanaka, Satoru y Shinichiro Kado. "Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station". En Reflections on the Fukushima Daiichi Nuclear Accident, 51–83. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-12090-4_3.

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Abe, Hiroyasu. "Ground Motion Prediction for Regional Seismic Risk Analysis Including Nuclear Power Station". En Resilience: A New Paradigm of Nuclear Safety, 221–27. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-58768-4_17.

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Tao, Chen, Zhang Jinlong, Liu Shan y Yu Benhai. "Fuzzy Real Option Analysis for IT Investment in Nuclear Power Station". En Computational Science – ICCS 2007, 953–59. Berlin, Heidelberg: Springer Berlin Heidelberg, 2007. http://dx.doi.org/10.1007/978-3-540-72588-6_152.

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Ren, Shuai y Hong Qian. "The Early Warning System of Nuclear Power Station Oriented to Human Reliability". En Communications in Computer and Information Science, 206–16. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-6364-0_21.

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Dong, Zhang-Xiao. "Design and Realization of Time Synchronization System for Nuclear Power Station DCS". En Lecture Notes in Electrical Engineering, 553–62. Singapore: Springer Nature Singapore, 2022. http://dx.doi.org/10.1007/978-981-19-1181-1_53.

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Chen, Ying-min, Hai-yan Deng y Fei Wang. "The Influence of Nitric Acid on Iron Ion on the Primary Loop of Nuclear Power Station". En Challenges of Power Engineering and Environment, 1037–39. Berlin, Heidelberg: Springer Berlin Heidelberg, 2007. http://dx.doi.org/10.1007/978-3-540-76694-0_191.

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Actas de conferencias sobre el tema "Windscale Nuclear Power Station"

Liu, Yuanyuan. "Nuclear Power Station Development History". En 7th International Conference on Education, Management, Information and Mechanical Engineering (EMIM 2017). Paris, France: Atlantis Press, 2017. http://dx.doi.org/10.2991/emim-17.2017.136.

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Asai, Yoshihisa, Toshimitsu Takagi y Tatsuya Azuma. "Major Component Replacement Experience in IKATA Power Station". En 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22618.

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Unit 1 & 2 in IKATA power station, both are two-loop PWRs, have experienced major component replacement. The components are two steam generators (SG) and a reactor pressure vessel closure head (VH) for each plant and were replaced with improved ones. This paper explains the reasons for the replacement and major improvements in the components.

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Bryson, Frank G. "Rational approach to nuclear power station IR surveys". En Orlando '90, 16-20 April. SPIE, 1990. http://dx.doi.org/10.1117/12.21909.

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Knox, A. M. "Plant life extension for Torness nuclear power station". En International Conference on Life Management of Power Plants. IEE, 1994. http://dx.doi.org/10.1049/cp:19941118.

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Zhang, Caiqing, Mi Zhang y Yuping Liu. "Economic Analysis of the Integrated Operation Mode of Nuclear Power Station and Pumped-storage Power Station". En International Conference on Humanities and Social Science 2016. Paris, France: Atlantis Press, 2016. http://dx.doi.org/10.2991/hss-26.2016.115.

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Mousa, Hamdi M., Sayed M. El-araby, Magdy A. Koutb y Elsayed H. M. Ali. "Evolutionary computation applictaion in power level control of nuclear power station". En 2012 Seventh International Conference on Computer Engineering & Systems (ICCES). IEEE, 2012. http://dx.doi.org/10.1109/icces.2012.6408484.

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Tian, Zhaohua y Qiang Li. "HL1000 Nuclear Power Station Emergency Borating System Capacity Demonstration". En 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-89471.

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Abstract Emergency Borating System has been widely used in the new third generation nuclear power plant in the world. HL1000 nuclear power plant is equipped with the Emergency Borating System (RBS) as an engineered safety facility, which provides the reactor the high pressure safety boron injection and long-term boration functions to ensure the core in subcritical. Firstly, the main functional requirements of RBS system of new third generation nuclear power plants in the world are introduced. Then, according to the two functional requirements for RBS of HL1000 nuclear power plant, reactivity control and confinements, the design criteria for RBS are determined. Based on these design criteria, the methodologies for RBS capacity demonstration are developed by the multi status point method. The relevant capacity parameters of RBS, including the maximum and minimum injection flow of RBS and the minimum volume requirements of boric acid tank are calculated separately.

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Allen, Wayne, David Anderson y Bert Mayer. "Pickering B Nuclear Power Generating Station Condenser Performance Improvement". En International Joint Power Generation Conference collocated with TurboExpo 2003. ASMEDC, 2003. http://dx.doi.org/10.1115/ijpgc2003-40036.

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The Ontario Power Generation (OPG) Pickering B Facility consists of four 540 MW nuclear generating units. Each unit is furnished with a once-through Condenser Cooling Water (CCW) System that uses Lake Ontario water. Zebra mussels (Dreissena polymorpha) are infesting the condenser cooling water intakes at Pickering. The mature mussels and their shells become entrained in the CCW, are deposited in the condenser inlet water boxes, and become lodged in the condenser tube sheets and within the tubes. As a result, the flow through the condenser is reduced, and the existing Condenser Tube Cleaning System (CTCS) performance is degraded. This reduces the Turbine-Generator generating capability that results in a loss of electric generation revenues for OPG, and increased maintenance costs to manually remove the zebra mussels from the condenser. OPG decided to install Debris Filters in the six 72-inch diameter inlets of each of the four Pickering B units to automatically remove the zebra mussels before they enter the condensers and discharge them back into the lake. The Debris Filters for Unit 8 were installed during a scheduled outage in the winter of 2001/2002. The Unit 5 installation was completed at the end of 2002 and the Unit 6 & 7 installations are scheduled for 2003. The installed equipment is performing as expected. The zebra mussels are intercepted by the Debris Filter, and are automatically discharged into the condenser bypass and returned to the lake. The CTCS system can again perform its intended function to prevent bio-fouling buildup inside the condenser tubes. As a result, generation capacity increased and maintenance expenditures decreased with a net result of increased revenues for OPG.

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Yang Hu, Yimin Zhou y Xiaoyun Li. "Radiation distribution prediction model of the nuclear power station". En 2016 IEEE 25th International Symposium on Industrial Electronics (ISIE). IEEE, 2016. http://dx.doi.org/10.1109/isie.2016.7744962.

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Qing, Cao, Wu Yimin y Zhang Zhimin. "Analysis of Thermal Shock on Nuclear Power Station Pump". En 1998 2nd International Pipeline Conference. American Society of Mechanical Engineers, 1998. http://dx.doi.org/10.1115/ipc1998-2129.

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In this paper, a heat conduction equation and a dynamic thermoelastic equation are briefly deduced and established based on Continuum Mechanics. First, an qualitative discussion is emphatically centered around the couple term and the dynamic term of the equation by means of the dimensional analysis and by considering the combination of the characteristics of the materials and of the thermal load effected on the nuclear power station pump under study. Second, formulations of the FEM for non-coupled heated equations and quasi-static thermoelastic equations are derived in this paper. Third, a half space thermal shock problem is used as a computational example in the highlighted research on the varying behavior of the dynamic thermal stress on the temperature slope. The conclusion of the paper provides reliable justification for applying the numerical method. Finally, the distribution and variety of the temperature field, the thermal stress field and the thermal deformation field at various transient moments on the pump are given.

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Informes sobre el tema "Windscale Nuclear Power Station"

Galyean, W. y D. Kelly. Containment venting analysis for the Shoreham Nuclear Power Station. Office of Scientific and Technical Information (OSTI), marzo de 1991. http://dx.doi.org/10.2172/5890518.

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Kaminski, M. D., L. Nunez y A. Purohit. Decontamination of control rod housing from Palisades Nuclear Power Station. Office of Scientific and Technical Information (OSTI), mayo de 1999. http://dx.doi.org/10.2172/12083.

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Noshkin, V. E., K. M. Wong, R. J. Eagle, J. W. Dawson, J. L. Brunk y T. A. Jokela. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station. Office of Scientific and Technical Information (OSTI), marzo de 1985. http://dx.doi.org/10.2172/5743313.

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SULLIVAN, T. ASSESSMENT OF RADIONUCLIDE RELEASE FROM CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION. Office of Scientific and Technical Information (OSTI), marzo de 2004. http://dx.doi.org/10.2172/15016581.

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Vojtech, R. J. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area. Office of Scientific and Technical Information (OSTI), marzo de 1994. http://dx.doi.org/10.2172/10152977.

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Noshkin, V. E., K. M. Wong, R. J. Eagle, J. L. Brunk y T. A. Jokela. Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station, 1985. Office of Scientific and Technical Information (OSTI), febrero de 1986. http://dx.doi.org/10.2172/5683150.

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Robison, W. L., Kai M. Wong y H. E. Jones. Environmental radiological studies in 1989 near the Rancho Seco Nuclear Power Generating Station. Office of Scientific and Technical Information (OSTI), noviembre de 1990. http://dx.doi.org/10.2172/6273385.

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Wesley, D. A., D. K. Nakaki, H. Hadidi-Tamjed y T. R. Kipp. Pressure-dependent fragilities for piping components: Pilot study on Davis-Besse Nuclear Power Station. Office of Scientific and Technical Information (OSTI), octubre de 1990. http://dx.doi.org/10.2172/6387566.

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Bonino, A., L. Pizarro, Z. Higa, S. A. Dupree y J. L. Schoeneman. Results of the first year of operation at Embalse Nuclear Power Station in Argentina. Office of Scientific and Technical Information (OSTI), julio de 1996. http://dx.doi.org/10.2172/270679.

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GREENE, G. A. y J. G. GUPPY. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA. Office of Scientific and Technical Information (OSTI), agosto de 1998. http://dx.doi.org/10.2172/760987.

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