Готові списки джерел за темами / Unit of nuclear power plant

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Добірка наукової літератури з теми "Unit of nuclear power plant"

Автор: Grafiati
Опубліковано: 30 травня 2022
Оновлено: 31 травня 2022

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Статті в журналах з теми "Unit of nuclear power plant"

1

Pavelyev, Egor, and Sergey Lavrinenko. "Performance of the Nuclear Power Plant Condensing Unit." MATEC Web of Conferences 72 (2016): 01085. http://dx.doi.org/10.1051/matecconf/20167201085.

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2

Zsilák, Mihály, and Valéria Nagy. "Innovation at Paks Nuclear Power Plant." Analecta Technica Szegedinensia 10, no. 2 (June 15, 2016): 36–41. http://dx.doi.org/10.14232/analecta.2016.2.36-41.

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Анотація:
In the summer of 2014 at the Maintenance Division of Paks Nuclear Power Plant Ltd. in Hungary there was an opportunity to take part in the preparatory work a new and innovative project for introduction. This is a charge-planner software support using the tests related the new fuel. The necessary calculations were completed and after obtaining the results the conclusion is that the actual 12 month operating period – the so-called campaign length – can be increased to 15 months, by using and shuffling the new fuel with higher enrichment, and by loading six fuel assemblies with gadolinium oxide into the unit. Conclusion is the new Gd-2_4.7 fuel initial expectations were met and managed to find a favorable average enrichment not only considering nuclear physics, but also economic, risk management, material structure and security points of view as well. Testing can be started in the summer of 2015, and the fuel can be loaded into Unit 3 for a test period of 365 days.
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3

Morita, Y., H. Mizouchi, M. Pellegini, H. Suzuki, and M. Naito. "ICONE23-1794 ACCIDENT ANALYSIS OF FUKUSHIMA DAIICHI NUCLEAR POWER PLANT UNIT 1 BY THE SAMPSON SEVEREACCIDENTCODE." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_383.

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4

Tan, Jin, Yue Feng Huang, and Zheng Xu. "Detailed Nuclear Power Plant Model for Power System Analysis Based on Matlab-Simulink." Applied Mechanics and Materials 291-294 (February 2013): 561–70. http://dx.doi.org/10.4028/www.scientific.net/amm.291-294.561.

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To research the load-following capability of the nuclear power generating unit, this paper proposed a detailed mathematical model of the pressurized water reactor (PWR) which is suitable for medium- and long-term stability analysis of power systems. Analyzed the interactions between the nuclear power generating unit and the power system, through the simulations of a single machine infinite bus (SMIB) system. The results show that PWR nuclear power generating unit can meet load following requirements to some degree.
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5

Dolgov, V. N. "Inherently safe power-generating unit for an underground nuclear power plant." Atomic Energy 76, no. 2 (February 1994): 136–38. http://dx.doi.org/10.1007/bf02414358.

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6

Takahashi, Atsuo, Marco Pellegrini, Hideo Mizouchi, Hiroaki Suzuki, and Masanori Naitoh. "ICONE23-1517 SIMULATION ANALYSIS ON ACCIDENT AT FUKUSHIMA DAIICHI NUCLEAR POWER PLANT UNIT 2 BY SAMPSON CODE." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_237.

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7

Alekseev, P. N., V. M. Mordashev, A. A. Proshkin, V. A. Stukalov, S. A. Subbotin, V. F. Tsibul’skii, and Yu F. Chernilin. "Choice of the unit power-generating capacity of a nuclear power plant." Atomic Energy 105, no. 5 (November 2008): 309–15. http://dx.doi.org/10.1007/s10512-009-9101-x.

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8

Modarres, Mohammad, Taotao Zhou, and Mahmoud Massoud. "Advances in multi-unit nuclear power plant probabilistic risk assessment." Reliability Engineering & System Safety 157 (January 2017): 87–100. http://dx.doi.org/10.1016/j.ress.2016.08.005.

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9

Feng, Wanxin, Zhixin Xu, Mingzhu Zhang, and Yu Yu. "Probabilistic Safety Analysis for Loss of Offsite Power Accident in Dual-units Nuclear Power Plant." E3S Web of Conferences 245 (2021): 01015. http://dx.doi.org/10.1051/e3sconf/202124501015.

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Анотація:
In order to explore the risk assessment method of the multi-unit nuclear power plant site, this paper selects the dual-unit plant nuclear site to analyze lose off-site power accident. By combining and improving the single-unit ET/FT model, to establish the dual-unit ET/FT model. From the analysis of the accident sequence, it can be concluded that the common cause failure of equipment is the main challenge faced by the dual-units. Especially the RPC sub-channel in the reactor protection system and the failure of emergency diesel engine circuit breaker. As can be seen from the high proportion of core CD occurring simultaneously in both uints, it has a great significance to study the risk of mult-units sites.
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10

Ершов, G. Ershov, Антонов, Aleksandr Antonov, Морозова, and O. Morozova. "Increase of Economic Efficiency of Nuclear Power Plant Unit Operation with Consideration of Safety Assurance." Safety in Technosphere 3, no. 4 (August 25, 2014): 67–71. http://dx.doi.org/10.12737/5307.

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Анотація:
High requirements are imposed on economic efficiency of nuclear power plant units operation. Obvious way of increasing economic benefit of nuclear power plant units operation is increasing the amount of generated electricity. The article describes a method of increasing economic benefit of nuclear power plant units by shortening its downtime due to scheduled maintenance and repair. As safety assurance is the top priority during nuclear power plant units operation, increase of economic viability of nuclear power plant units should be carried out with this consideration, which is the distinctive feature of the proposed method.
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Дисертації з теми "Unit of nuclear power plant"

1

Barner, Robert Buckner. "Power conversion unit studies for the next generation nuclear plant coupled to a high-temperature steam electrolysis facility." Texas A&M University, 2006. http://hdl.handle.net/1969.1/4835.

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The Department of Energy and the Idaho National Laboratory are developing a Next Generation Nuclear Plant (NGNP) to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold: 1) efficient low cost energy generation and 2) hydrogen production. Although a next generation plant could be developed as a single-purpose facility, early designs are expected to be dual-purpose. While hydrogen production and advanced energy cycles are still in their early stages of development, research towards coupling a high temperature reactor, electrical generation and hydrogen production is under way. Many aspects of the NGNP must be researched and developed to make recommendations on the final design of the plant. Parameters such as working conditions, cycle components, working fluids, and power conversion unit configurations must be understood. Three configurations of the power conversion unit were modeled using the process code HYSYS; a three-shaft design with 3 turbines and 4 compressors, a combined cycle with a Brayton top cycle and a Rankine bottoming cycle, and a reheated cycle with 3 stages of reheat were investigated. A high temperature steam electrolysis hydrogen production plant was coupled to the reactor and power conversion unit by means of an intermediate heat transport loop. Helium, CO2, and an 80% nitrogen, 20% helium mixture (by weight) were studied to determine the best working fluid in terms cycle efficiency and development cost. In each of these configurations the relative heat exchanger size and turbomachinery work were estimated for the different working fluids. Parametric studies away from the baseline values of the three-shaft and combined cycles were performed to determine the effect of varying conditions in the cycle. Recommendations on the optimal working fluid for each configuration were made. The helium working fluid produced the highest overall plant efficiency for the three-shaft and reheat cycle; however, the nitrogen-helium mixture produced similar efficiency with smaller component sizes. The CO2 working fluid is recommend in the combined cycle configuration.
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2

Greyvenstein, Renée. "Techno-economic comparison of power conversion units for the next generation nuclear plant / R. Greyvenstein." Thesis, North-West University, 2005. http://hdl.handle.net/10394/4481.

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3

Лукинова, Дарина Андреевна, Валерий Петрович Северин та Елена Николаевна Никулина. "Оптимизация показателей качества систем автоматического управления ядерным реактором ВВЭР-1000". Thesis, Національний університет біоресурсів і природокористування України, 2017. http://repository.kpi.kharkov.ua/handle/KhPI-Press/33125.

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Анотація:
Представлены результаты математического моделирования систем автоматического регулирования мощности ядерного реактора ВВЭР-1000. Применены методы оптимизации прямых показателей качества систем автоматического регулирования мощности ядерного реактора с различными типами регуляторов.
The results of mathematical modeling of automatic control systems of power of the nuclear reactor WWER-1000 are presented. The technique of optimization of direct quality indexes of automatic regulation system of power of a nuclear reactor with various types of regulators is applied.
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4

Нікуліна, Олена Миколаївна, Валерій Петрович Северин та Ніна Вікторівна Трубчанова. "Математичні моделі систем управління парогенератором енергоблоку АЕС". Thesis, НТУ "ХПІ", 2017. http://repository.kpi.kharkov.ua/handle/KhPI-Press/33421.

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Анотація:
Розроблена математична модель системи автоматичного управління продуктивністю парогенератора, яка представлена в просторі станів з відносними змінними у вигляді системи диференціальних рівнянь. Розв’язані задачі ідентифікації параметрів моделей систем керування за експериментальними даними процесів в парогенераторі ПГВ-1000.
The mathematical model of the system of automatic control of the efficiency of a steam generator, which is presented in the space of states with relative variables in the form of a system of differential equations, is developed. Problems of parameters identification of control systems models based on experimental data of processes in steam generator PGV-1000 were solved.
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Северин, Валерий Петрович, Елена Николаевна Никулина та Дарина Андреевна Лукинова. "Многокритериальный синтез систем управления энергоблока АЭС с реактором ВВЭР-1000 для эксплуатации в маневренных режимах". Thesis, НТУ "ХПІ", 2017. http://repository.kpi.kharkov.ua/handle/KhPI-Press/33422.

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Анотація:
Для многокритериального синтеза нелинейных систем управления использована упрощенная векторная целевая функция, которая учитывает ограничения переменных параметров, ограничения перерегулирования и размаха колебаний, а также требования минимальности времени регулирования. Как пример задачи синтеза системы управления энергоблока при работе в маневренных режимах рассматривается задача многокритериального синтеза системы управления турбиной с нечеткими регуляторами.
For a multicriterion synthesis of nonlinear control systems, a simplified vector objective function is used that takes into account the limitations of the variable parameters, the limitations of overshoot and swing of the oscillations, and also the requirements for the minimum of the control time. As an example of the task of synthesizing the power unit control system during operation in maneuvering modes, the task of multi-criteria synthesis of the turbine control system with fuzzy regulators is considered.
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6

Veselý, Libor. "Obnova hřídele vzduchotechnického soustrojí." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2017. http://www.nusl.cz/ntk/nusl-318151.

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Анотація:
The subject of this work is the repair of an air-handling unit. Possible causes of the problem are analyzed and multiple solutions are proposed. The first variant considers the refurbishment of the damaged component using thermal spray technology, including the choice of the best method. The second solution proposes the manufacture of a new part using machining in the environment of the company. This process requires an intermediate product to be made, and the choice of the correct machines from what the company has available, choice of the right tools and cutting conditions. The technical-economical evaluation compares the the expenses tied with both of the solutions. The chosen repair solution was used for the repair of the air-handling unit.
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7

Ludvík, Lubomír. "Náhřev a spouštění jaderného bloku Elektrárny Dukovany po odstávce." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2016. http://www.nusl.cz/ntk/nusl-242192.

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This thesis deals with the analysis of warming and starting up the nuclear unit of Dukovany NPP after the outage. First part explains the various operating modes of nuclear power plants, specifically operating modes of Dukovany NPP. The following part contains the analysis of heat sources in the primary circuit and also the individual production and consumption of steam by the NPP. The next part deals with division into several points of the warming of the Dukovany NPP. The analysis of warming nuclear unit after a outage is made on the basis of the industry based data, measured in December 2015. The result of the analysis is determination the amount of steam passing from a another nuclear unit, which is following by the own proposal of the external steam source.
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8

Северин, Валерій Петрович. "Синтез систем керування енергоблоку атомної електростанції методами векторної оптимізації". Thesis, Львівська політехніка, 2011. http://repository.kpi.kharkov.ua/handle/KhPI-Press/32716.

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Анотація:
Представлені проблеми синтезу систем автоматичного управління на основі методів векторної оптимізації прямих показників якості та покращеної інтегральної квадратичної оцінки. Побудовані математичні моделі систем керування енергоблоком атомної електростанції для нормальних режимів. Наведено результати синтезу оптимальних ПІД та нечітких регуляторів.
Problems of synthesis of automatic control systems based on the methods of vector optimization of direct quality indices and improved integral quadratic estimate are presented. Mathematical models of control systems for power unit of nuclear electric station for normal modes are constructed. The results of synthesis of optimal PID and fuzzy controllers are presented.
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9

Северин, Валерий Петрович. "Синтез систем управления энергоблока АЭС в лаборатории оптимизации OPTLAB". Thesis, ТЕС, 2015. http://repository.kpi.kharkov.ua/handle/KhPI-Press/43189.

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Анотація:
Рассмотрена лаборатория методов оптимизации, которая построена на принципах модульности, простоты и надежности. Выполнен синтез оптимальных систем управления для ядерного реактора, парогенератора и паровой турбины, а также систем автоматического поддержания нейтронной мощности и давления пара перед турбиной для нормальных режимов эксплуатации энергоблока.
Consideration was given to the laboratory of optimization methods based on the principles of the modularity, simplicity and reliability. Optimal automatic control systems for the nuclear reactor, steam generator, steam turbine and automatic maintenance of the neutron power and the pressure before the turbine for normal operation modes were synthesized.
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Северин, Валерий Петрович, Елена Николаевна Никулина та Дарина Андреевна Лютенко. "Анализ и синтез систем управления энергоблока АЭС для маневренных режимов эксплуатации". Thesis, Сумський державний університет, 2016. http://repository.kpi.kharkov.ua/handle/KhPI-Press/33429.

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Анотація:
Усовершенствованы модели и методы для анализа и синтеза систем автоматического управления энергоблоков атомных электростанций на основании методов оптимизации. Построены нелинейные математические модели систем управления энергоблока и проведен синтез оптимальных регуляторов для маневренных режимов эксплуатации.
Models and methods for analysis and synthesis of automatic control systems of power units of nuclear power plants were improved on the basis of optimization methods. Nonlinear mathematical models of control systems of power unit were built and synthesis of optimal controllers was carried out for maneuvering modes of operation.
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Книги з теми "Unit of nuclear power plant"

1

Program, Maryland Power Plant Research. Environmental review of proposed Unit 3 at Calvert Cliffs Nuclear Power Plant. Annapolis, MD: Maryland Power Plant Research Program, 2011.

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2

Vo, T. V. PRA applications program for inspection at Calvert Cliffs Unit 1 nuclear power plant. Washington, DC: Division of Radiation Protection and Emergency Preparedness, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989.

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3

Regulation, U. S. Nuclear Regulatory Commission Office of Nuclear Reactor. Generic environmental impact statement for license renewal of nuclear plants: Regarding Grand Gulf Nuclear Powerplant, unit 1 : final report. Washington, DC: United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 2014.

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4

Regulation, U. S. Nuclear Regulatory Commission Office of Nuclear Reactor. Safety evaluation report related to operation of Watts Bar Nuclear Plant, Unit 2. Washington, D.C: United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 2015.

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5

Generic environmental impact statement for license renewal of nuclear plants: Supplement 51, regarding Callaway Plant, Unit 1, draft report for comment. Washington, DC: United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 2014.

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6

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, unit 2. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 2013.

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7

Regulation, U. S. Nuclear Regulatory Commission Office of Nuclear Reactor. Draft environmental statement for decommissioning Humboldt Bay Power Plant, Unit no. 3, docket no. 50-133: Pacific Gas and Electric Company. Washington, D.C: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1986.

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8

Regulation, U. S. Nuclear Regulatory Commission Office of Nuclear Reactor. Technical specifications Diablo Canyon Nuclear Power Plant, Unit no. 2, docket no. 50-323: Appendix "A" to license no. DPR-81. Washington, D.C: The Commission, 1985.

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9

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2, docket no. 50-320: Final supplement dealing with post-defueling monitored storage and subsequent cleanup. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1989.

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10

Regulation, U. S. Nuclear Regulatory Commission Office of Nuclear Reactor. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2, docket no. 50-320: Draft supplement dealing with post-defueling monitored storage and subsequent cleanup. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1989.

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Частини книг з теми "Unit of nuclear power plant"

1

Rumyantsev, Konstantin E., Sergey L. Balabaev, and Irina Yu Balabaeva. "Fuel Assembly Height Measurements at the Nuclear Power Plant Unit Active Zone." In Communications in Computer and Information Science, 156–63. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-5780-9_14.

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2

Bin, Zeng, and Zhao Yang. "Analysis and Summarization of Continuous Spray Test on Pressurizer of Fuqing Nuclear Power Plant Unit 1." In Proceedings of The 20th Pacific Basin Nuclear Conference, 31–37. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2317-0_4.

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3

Paliwal, Nikhil, Laxmi Srivastava, Manjaree Pandit, and Poonam Singh. "Jaya Algorithm-Based Load Frequency Control in Nuclear Power Plant Incorporating Energy Storage Unit." In Artificial Intelligence and Sustainable Computing, 239–52. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-1220-6_21.

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4

Xi, Wang, Wei Liu, Tao Bai, and Ji Shi. "A Study About Unit Testing for Embedded Software of Control System in Nuclear Power Plant." In Lecture Notes in Electrical Engineering, 157–63. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-3456-7_17.

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5

Bologna, S., M. Minichino, D. Del Corso, F. Maddaleno, and E. Pasero. "Testing of a Hardware Unit of a Nuclear Power Plant Protection System — the IEEE 796 Bus." In Achieving Safety and Reliability with Computer Systems, 218–31. Dordrecht: Springer Netherlands, 1987. http://dx.doi.org/10.1007/978-94-009-3461-0_18.

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6

Zheng, Dongjia. "Conclusion of the Test of Fujian Fuqing Nuclear Power Plant Unit 1 Determination of Reactor Coolant Flow on the Basis of the Heat Balance." In Proceedings of The 20th Pacific Basin Nuclear Conference, 67–73. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2317-0_8.

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7

Pekár, Ivan, and Ján Doni. "Safety Coordination in Large Construction Project (Completion Process of Unit 3 and 4, Mochovce Nuclear Power Plant, Slovak Republic)." In Advances in Intelligent Systems and Computing, 41–46. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-41929-9_5.

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8

Jung, Woo Sik, Joon-Eon Yang, and Jaejoo Ha. "An Approach to Estimate SBO Risks in Multi-unit Nuclear Power Plants with a Shared Alternate AC Power Source." In Probabilistic Safety Assessment and Management, 2997–3002. London: Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_480.

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9

Brumovský, Milan, Martin Ruščák, and Jirí Žďárek. "Plant Life Management Programme Preparation for WWER440/V-213C Units in Czech Republic." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 733–39. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch76.

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10

Grytsenko, O. V., S. M. Pugach, V. L. Diemokhin, V. N. Bukanov, M. Marek, and S. Vandlik. "Exposure Conditions of Reactor Internals of Rovno VVER-440 Nuclear Power Plant Units 1 and 2." In Reactor Dosimetry: 14th International Symposium, 92–98. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp49605t.

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Тези доповідей конференцій з теми "Unit of nuclear power plant"

1

Kemp, Petrus D., and Chris Nieuwoudt. "Operation and Control of the PBMR Demonstration Power Plant." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89359.

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A large interest in High Temperature Gas-cooled Reactors (HTGR) has been shown in recent years. HTGR power plants show a number of advantages over existing technology including improved safety, modular design and high temperatures for process heat applications. HTGR plants with closed loop direct cycle power conversion units have unique transient responses which is different from existing nuclear plants as well as conventional non-nuclear power plants. The operation and control for a HTGR power plant therefore poses new and different challenges. This paper describes the modes of operation for the Pebble Bed Modular Reactor (PBMR) demonstration plant. The PBMR demonstration plant is an advanced helium-cooled, graphite-moderated HTGR consisting of a closed loop direct cycle power conversion unit. The use of transient analysis simulation makes it possible to develop effective control strategies and design controllers for use in the power conversion unit as well as the reactor. In addition to plant controllers the operator tasks and operational technical specifications can be developed and evaluated making use of transient analysis simulation of the plant together with the control system. The main challenges in the operation and control of the reactor and power conversion unit are highlighted with simulation results. Control strategies in different operating regions are shown and results for the power conversion unit start-up transition and the loss of the grid connection during power operation are presented.
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2

Xu, YanHui, ZhenZhen Wang, Wen Sun, ShiHe Chen, YuZhong Wu, and Bing Zhao. "Unit commitment model considering nuclear power plant load following." In 2011 IEEE International Conference on Advanced Power System Automation and Protection (APAP). IEEE, 2011. http://dx.doi.org/10.1109/apap.2011.6180663.

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3

Anderson, Myron R. "Steam Generator Replacement Project at TVA’s Sequoyah Unit 1 Nuclear Power Plant." In ASME 2004 Power Conference. ASMEDC, 2004. http://dx.doi.org/10.1115/power2004-52069.

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Pressurized Water Reactor Power Plants have at times required that large components be replaced (steam generators weighing 750,000 lbs) which have necessitated performing first time modifications to the plant that were unintended during the original design. The steam generator replacement project at Tennessee Valley Authority (TVA’s) Sequoyah Nuclear Power Station necessitated (1) two large temporary openings (21’×45’) in the plant’s Shield Building roof (2’ thick concrete) by hydro-blasting to allow the removal of the old generators and installation of the new, (2) removal and repair of the concrete steam generator enclosure roofs (20’ diameter, 3’ thick) which were removed by wire saw cutting and (3) the seismic qualification of; the design and construction of an extensive ring foundation for; the use of one of the world largest cranes to remove these components through the roof. This removal and replacement process had to be performed in an expeditious manner to minimize the amount of time the plant is shutdown so the plant could return to providing power to the grid. This paper will address some of the many technical and construction considerations required to perform this demolition and repair work safely, efficiently and in a short as possible duration.
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4

Zhou, Taotao, Mohammad Modarres, and Enrique López Droguett. "A Review of Multi-Unit Nuclear Power Plant Probabilistic Risk Assessment Research." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81130.

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The events at the Fukushima nuclear power station drew attention to the need for consideration of risks from multiple nuclear reactor units co-located at a site. As a result, considerable international interests and research efforts have been dedicated to addressing the multi-unit risks over the past few years. This paper presents a review of the state-of-the-art multi-unit probabilistic risk assessment (MUPRA) of nuclear power plants. The concept of MUPRA is briefly presented and the relevant activities to address and develop methodologies are summarized including workshops, proceedings, projects and case studies. The paper presents different facets of MUPRA research, including multi-unit event, MUPRA modeling and site-based risk metric. The paper also identifies existing gaps and the need for future research.
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5

Liu, Heng, Yue Chen, Fuping Li, Hui Liu, and Shunlong Yang. "The Chemistry Experience Summary During the Engineering Commissioning Period of Fujian Ningde Nuclear Power Plant." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67040.

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In chemical researchers view, hot functional test is a verification of the Nuclear Power Plant before first fuel loading and commercial operation, which is the preparation for staffs, documents, instruments and sampling systems. So, chemistry department should use its own language, knowledge and experience to express their thoughts and what they have seen during the engineering commissioning period. As the first commercial operation nuclear power plant after Fukushima nuclear accident, during the four units commissioning period, chemical researchers accumulated a lot of good experience and feedbacks in the aspect of construction and commissioning for new nuclear power plant. For example, in order to ensure the personnel skill level, we must make special plans which include staff training, laboratory construction, instrument and on-line system commissioning, and all of these should be timely adjusted and changed in order to be consistent with the engineering progress. In order to ensure the water quality of pipe flushing in different stages, such as cold functional test, hot functional test, we should set a strictly water chemical standard which based on the HAF103, and the standard should have some differences in different stage for one unit. In order to ensure the water chemistry in good performance especially after the unit going into commercial operation, the maintenance plan for equipment and system must be formulated, and then, a detailed monitoring plan must be executed. At the same time, a strict system flushing controlling mode can also provide a great benefits for water chemistry quality, especially in the period of start-up. In addition to these above experiences, chemistry researchers of Ningde nuclear power plant also accumulated a lot of good practices and feedbacks about dealing with some abnormal water quality activities, which can’t be founded in commercial operation unit. For example, the aluminum (Al) content in the primary increased rapidly and beyond the specification limits in hot functional test and so on. This article will share the good practices and feedbacks of the first phase of Fujian Ningde nuclear power plant. We hope these good practices and experience feedbacks can provide good reference for the other new nuclear plants in the stage of design, construction, operation and maintenance in the future.
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6

Naitoh, Masanori, Hiroaki Suzuki, and Hidetoshi Okada. "Function of Isolation Condenser of Fukushima Unit-1 Nuclear Power Plant." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-55239.

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Анотація:
The Tohoku Region Pacific Coast Earthquake with magnitude 9.0 occurred at 2:46 PM of March 11th, 2011, followed by a huge Tsunami. The Fukushima Daiichi nuclear power station suffered serious damages from the Tsunami, involving core melt and release of large amount of fission products to an environment. The station blackout (SBO) occurred due to submergence of emergency equipment by the sea water. The isolation condenser (IC) was the only device for decay heat removal at the unit-1 of the Fukushima Daiichi nuclear power station after the reactor scram. The IC function was analyzed with a severe accident analysis code SAMPSON. The analysis results showed that (1) core melt resulting in RPV failure occurred since the IC operation was limited because it was not designed as a countermeasure to mitigate severe accident progression in Japan and (2) even assuming the continuous IC operation after the SBO to mitigate severe accident progression, the RPV failure occurred at 18:52, March 12th. However, since the alternate water injection by a fire engine was actually ready to start at 5:46, March 12th, which was earlier than calculated RPV failure time, the RPV failure could be prevented by continuous IC operation.
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7

Brickstad, Bjorn, Adam Letzter, Arturas Klimasauskas, Robertas Alzbutas, Linas Nedzinskas, and Vytis Kopustinskas. "Risk Based Inspection Pilot Study of Ignalina Nuclear Power Plant, Unit 2." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22621.

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A project with the acronym IRBIS (Ignalina Risk Based Inspection pilot Study) has been performed with the objective to perform a quantitative risk analysis of a total of 1240 stainless steel welds in Ignalina Nuclear Power Plant, unit 2 (INPP-2). The damage mechanism is IGSCC and the failure probabilities are quantified by using probabilistic fracture mechanics. The conditional core damage probabilities are taken from the plant PSA.
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8

Saxon, George, and William Moye. "South Texas Project Nuclear Power Plant Unit 1 Condenser: Scale Deposit Removal From 96,234 Condenser Tubes." In ASME 2007 Power Conference. ASMEDC, 2007. http://dx.doi.org/10.1115/power2007-22148.

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South Texas Project (STP) Nuclear Power Plant was commissioned for operation in 1988. There are two units, Unit 1 and Unit 2, similar in design and capacity. Unit 1 is base loaded and produces 1,250 megawatts of power. There are 96,234 titanium condenser tubes, size 3/4” O.D. by 22 BWG in the multi-stage condenser. The tubes in the condenser were known to be fouled with calcium carbonate; however the extent of the fouling was unknown prior to the outage. The last effective cleaning on the Unit 1 condenser had been conducted five years ago in 2001 and only thin calcium deposits were noted at that time. It is well known that fouling of the condenser can have significant impact on unit operations: It increases unit heat rate and it can also limit unit generation capacity. However, due to the size and capacity of a condenser, and the heat transfer characteristics of a deposit type, fouling may go unrecognized until the deposition rate reaches an advanced level. As was the case at the South Texas Project Nuclear Power Plant in Wadsworth, Texas, where scale build up in the condenser tubes had not only developed, hardened, and thickened over time, but had also rendered many of the tubes completely blocked and useless. The tenacious scale, when combined with the large size of the condenser, made returning the condenser to its new and clean condition an extremely challenging project. A comprehensive cleaning project was planned and executed in September, 2006 cleaning all 96,234 titanium condenser tubes utilizing innovative scale cutting technology and mechanical scrapers. The completion of the project resulted in virtually all tubes being opened, clean, and available for service. This paper will acquaint you with the project from its conception to fruition and report the outcome.
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9

Fei, Liu. "Periodic Tests Improvement of Emergency Diesel Generator Units in Nuclear Power Plant." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16105.

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Abstract Domestic diesel-generator units of M310 reactor nuclear power plants at present adopt the French standard RCC-E 2005 emergency for periodic tests. During low-power periodic tests, the diesel-generators are not adequately protected, and there is a risk of serious damage to equipment. This article analyzes in detail the provisions of the IEEE 387 standard for the periodic tests of emergency diesel-generator unit, improves the periodic tests of the emergency diesel-generator unit according to the IEEE 387 standard, cancels the original low-power tests, and uses the test during the normal operation of the unit in order to solve this problem. The grid-connected test method and detailed analysis of the improved test content make the EDG periodic test method more economical and safe. The improvement has been approved by the nuclear safety regulatory agency, which provides an important reference for the related periodic test improvement of nuclear power plants.
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10

Zou, Shengjia, Ming Zhao, Deyi Liu, Naiyuan Zhang, Yang Luo, Li Wang, Jianguo Zhang, and Honghao Chen. "Probabilistic Safety Assessment on Unavailability of Auxiliary External Power Supply in Fangjiashan Nuclear Power Plant." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-64590.

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Abstract The auxiliary external power Qinfang 2P70 of Fangjiashan NPP need to be shutdown, which makes one way the external power unavailable, thus affecting the safety level of the plant. In this paper, Through the internal event level PSA model, internal event LERF model, internal fire model and internal water flooded model, during Fangjiashan at power, 2P70 shut down caused one way the external power unavailable, gives the safety assessment results, And put forward the close attention of the important equipment such as the main power grid and the diesel engine. The test and maintenance of the diesel engine and the SEC/RRI heat exchanger are prohibited. The risk of the unit is managed and controlled by a series of other measures. The risk monitor is used to supervise the unit in real time. Finally, the application risk monitor of the power plant is discussed. The necessity and the PSA method to evaluate the possibility of auxiliary transformer shutdown to generalize to generating units.
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Звіти організацій з теми "Unit of nuclear power plant"

1

Abbott, L. Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant. Office of Scientific and Technical Information (OSTI), September 1985. http://dx.doi.org/10.2172/6051787.

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2

Gore, B. F., T. V. Vo, and D. G. Harrison. Auxiliary feedwater system risk-based inspection guide for the Diablo Canyon Unit 1 Nuclear Power Plant. Office of Scientific and Technical Information (OSTI), August 1990. http://dx.doi.org/10.2172/6546020.

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3

Vo, T., M. Harris, and B. Gore. PRA (probabilistic risk assessment) applications program for inspection at Calvert Cliffs Unit 1 Nuclear Power Plant. Office of Scientific and Technical Information (OSTI), June 1989. http://dx.doi.org/10.2172/5910160.

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4

Kullberg, C. RELAP5 thermal-hydraulic analysis of the SNUPPS (Standardized Nuclear Unit Power Plant System) pressurized water reactor. Office of Scientific and Technical Information (OSTI), May 1990. http://dx.doi.org/10.2172/6980402.

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5

McKay, S. L., and G. A. Coles. Peer review of the Barselina Level 1 probabilistic safety assessment of the Ignalina Nuclear Power Plant, Unit 2. Office of Scientific and Technical Information (OSTI), January 1995. http://dx.doi.org/10.2172/10110727.

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6

Wells, J. E., D. A. Lappa, D. L. Bernreuter, J. C. Chen, T. Y. Chuang, J. J. Johnson, R. D. Campbell, et al. Analysis of the LaSalle Unit 2 nuclear power plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 8, Seismic analysis. Office of Scientific and Technical Information (OSTI), November 1993. http://dx.doi.org/10.2172/10106923.

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7

Chung, Bud-Dong, Hho-Jung Kim, and Young-Jin Lee. Assessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU (Korea Nuclear Unit) No. 1 Plant. Office of Scientific and Technical Information (OSTI), April 1990. http://dx.doi.org/10.2172/7048725.

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8

Pugila, W. J. Analysis of core damage frequency: Nuclear power plant Dukovany, VVER/440 V-213 Unit 1, internal events. Volume 1: Main report. Office of Scientific and Technical Information (OSTI), December 1994. http://dx.doi.org/10.2172/74108.

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9

Burns, T. J., R. D. Cheverton, G. F. Flanagan, J. D. White, D. G. Ball, L. B. Lamonica, and R. Olson. Preliminary development of an integrated approach to the evaluation of pressurized thermal shock as applied to the Oconee Unit 1 Nuclear Power Plant. Office of Scientific and Technical Information (OSTI), May 1986. http://dx.doi.org/10.2172/5902522.

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SM Garrett. Joint U.S./Russian Study on the Development of a Preliminary Cost Estimate of the SAFSTOR Decommissioning Alternative for the Leningrad Nuclear Power Plant Unit #1. Office of Scientific and Technical Information (OSTI), September 1998. http://dx.doi.org/10.2172/1247.

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