Relevant bibliographies by topics / Nuclear power unit

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Nuclear power unit'

Author: Grafiati
Published: 30 May 2022
Last updated: 31 May 2022

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Journal articles on the topic "Nuclear power unit"

1

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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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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Ju, Yuntao, Jiankai Wang, Fuchao Ge, Yi Lin, Mingyu Dong, Dezhi Li, Kun Shi, and Haibo Zhang. "Unit Commitment Accommodating Large Scale Green Power." Applied Sciences 9, no. 8 (April 18, 2019): 1611. http://dx.doi.org/10.3390/app9081611.

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As more clean energy sources contribute to the electrical grid, the stress on generation scheduling for peak-shaving increases. This is a concern in several provinces of China that have many nuclear power plants, such as Guangdong and Fujian. Studies on the unit commitment (UC) problem involving the characteristics of both wind and nuclear generation are urgently needed. This paper first describes a model of nuclear power and wind power for the UC problem, and then establishes an objective function for the total cost of nuclear and thermal power units, including the cost of fuel, start-stop and peak-shaving. The operating constraints of multiple generation unit types, the security constraints of the transmission line, and the influence of non-gauss wind power uncertainty on the spinning reserve capacity of the system are considered. Meanwhile, a model of an energy storage system (ESS) is introduced to smooth the wind power uncertainty. Due to the prediction error of wind power, the spinning reserve capacity of the system will be affected by the uncertainty. Over-provisioning of spinning reserve capacity is avoided by introducing chance constraints. This is followed by the design of a UC model applied to different power sources, such as nuclear power, thermal power, uncertain wind power, and ESS. Finally, the feasibility of the UC model in the scheduling of a multi-type generation unit is verified by the modified IEEE RTS 24-bus system accommodating large scale green generation units.
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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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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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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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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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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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Fu, Wen Feng, Fe Li, and Lan Xin Zhou. "Application of PSO in the Optimization of Nuclear Power Unit’s Heat Regenerative System." Advanced Materials Research 986-987 (July 2014): 698–701. http://dx.doi.org/10.4028/www.scientific.net/amr.986-987.698.

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Based on theoretical deduction, according to the characteristics of nuclear power unit, a universal heat economic framework for PWR nuclear power plant heat regenerative system was established. And on this basis, the cycle thermal efficiency was chosen as the optimization goal, the extraction steam pressures were chosen as optimization variables, a universal nuclear power unit regenerative system optimization model was established. A 900 MW nuclear power unit was taken for example, it’s the first time that AWPSO was applied to optimize the regenerative heat system of nuclear power unit. The result shows that the convergence ability and search performance of PSO are superior to other methods and the original design scheme. A new and convenient design is provided for PWR nuclear power plant heat regenerative system in this paper.
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Cheng, Shou Yu, Xin Kai Liu, and Min Jun Peng. "Monitor & Diagnosis Support System for Nuclear Power Plants." Applied Mechanics and Materials 121-126 (October 2011): 4033–37. http://dx.doi.org/10.4028/www.scientific.net/amm.121-126.4033.

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An Monitor& Diagnosis Support System for Nuclear Power Plants (NPPMDS) is developed in the embedded real-time operation system VxWorks in this paper. NPPMCS includes data collection and validation unit, operation monitoring unit, fault diagnosis unit, alarm analysis unit, operation procedures and Human-machine interface and so on. The paper introduces the design and implementation of NPPMDS including the structure of the NPPMDS and the main function units. In order to confirm the validity of this system, the SGTR simulation experiment was carried out on a full scale simulator of nuclear power plants. The experimental results show that the system provides operation support, the load and pressure for the workers can be reduced and the safety of nuclear power plants can be enhanced.
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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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Dissertations / Theses on the topic "Nuclear power unit"

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Wu, Zhi. "Transmission expansion planning and unit commitment with large-scale integration of wind power." Thesis, University of Birmingham, 2016. http://etheses.bham.ac.uk//id/eprint/6738/.

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The large-scale integration of wind generation into the power system brings great challenges to transmission expansion planning (TEP) and unit commitment (UC). The intermittence nature of wind generation needs to be fully considered in these two problems, which stimulates the research of this thesis. The selection of candidate lines is the prerequisite for the TEP problem. Considering the limitations of manual selection approach, a method to select candidate lines automatically is proposed, which consists of five stages to reinforce existing corridors and new corridors. Results of the two test systems illustrate that the locational marginal price difference is neither sufficient nor necessary condition for candidate lines. The uncertainty of load demand and wind power is studied both in the TEP and UC problems. In the term of TEP, a two-stage stochastic formulation of TEP is proposed. The stochastic dual dynamic programming (SDDP) approach is applied to consider the uncertainty, and the whole model is solved by Benders decomposition (BD) technique. In the term of UC, the chance-constrained two-stage programming formulation is proposed for the day-ahead UC problem. The chance-constrained stochastic programming formulation is converted into an equivalent deterministic formulation by a sequence of approximation and verification.
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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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Лукинова, Дарина Андреевна, Валерий Петрович Северин, and 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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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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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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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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Нікуліна, Олена Миколаївна, Валерій Петрович Северин, and 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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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, and 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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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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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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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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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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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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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, and 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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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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Books on the topic "Nuclear power unit"

1

Kozaczka, Jarosław. Thermodynamics of modern conventional and nuclear power technologies: Unit operations. Tarnów: TANT Publishers, 2011.

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Vo, T. V. PRA applications program for inspection at Arkansas Nuclear One, Unit 1. King of Prussia, PA: Division of Reactor Projects, Region I, U.S. Nuclear Regulatory Commission, 1988.

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Gore, B. F. PRA applications program for inspection at Oconee Unit 3. King of Prussia, PA: Division of Reactor Projects, Region I, U.S. Nuclear Regulatory Commission, 1987.

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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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Alper, B. Active solar heating in the UK: Department of Energy R&D programme 1977-1984 : report from the Energy Technology Support Unit on the Department of Energy's R&D programme, 1977-1984. Harwell: Energy Technology Support Unit for the Department of Energy, 1985.

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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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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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Persinko, D. An investigation of the contributors to wrong unit or wrong train events. Washington, D.C: Division of Human Factors Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.

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U.S. Nuclear Regulatory Commission. Division of Site and Environmental Reviews. Supplemental environmental impact statement for the combined license (COL) for North Anna Power Station Unit 3: Final report. Washington, DC: United States Nuclear Regulatory Commission, 2010.

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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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Book chapters on the topic "Nuclear power unit"

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Hao, Jingyun, Dong Deng, Jing Wang, Shuangyin Wang, and Xiongfei Hua. "Radiography Inspection Technology of CPR1000 Nuclear Power Unit Pressurizer." In Energy Materials 2014, 539–44. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-48765-6_65.

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Hao, Jingyun, Dong Deng, Jing Wang, Shuangyin Wang, and Xiongfei Hua. "Radiography Inspection Technology of CPR1000 Nuclear Power Unit Pressurizer." In Energy Materials 2014, 539–44. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2015. http://dx.doi.org/10.1002/9781119027973.ch65.

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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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Zengwei. "Qinshan 300 MW Nuclear Power Unit Condensed Water Dissolved Oxygen on the High Side Cause Analysis." In Proceedings of The 20th Pacific Basin Nuclear Conference, 189–99. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2317-0_19.

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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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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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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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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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Ye, Jiaping, Jiang Wei, Qiang Liu, Feng Chen, and Shaoqun Song. "Over Excitation Limiter Oscillation Analysis and Damping Measures for ALSTOM Excitation System of Nuclear Power Unit." In Proceedings of PURPLE MOUNTAIN FORUM 2019-International Forum on Smart Grid Protection and Control, 125–41. Singapore: Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-9779-0_10.

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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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Conference papers on the topic "Nuclear power unit"

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Harrop, Grenville, and Bill P. Poirier. "Construction of Westinghouse AP1000™ Nuclear Power Plants in China." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30077.

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In July 2007, China entered a new era of sustainable, safe, and ecologically sound energy development by committing to build four AP1000™ units to be constructed in pairs at the coastal sites of Sanmen (Zhejiang Province) and Haiyang (Shandong Province). Both sites have the planned ability to accommodate at least six AP1000 units. The Westinghouse AP1000 is the only Generation III+ reactor to receive design certification from the U.S. Nuclear Regulatory Commission (NRC). With a design that is based on the proven performance of Westinghouse-designed pressurized water reactors (PWRs), the AP1000 is an advanced 1100 megawatt (MW) plant that uses the forces of nature and simplicity of design to enhance plant safety and operations. Excavation commenced for the first of four China AP1000 units in February 2008, and placement of the basemat concrete for Sanmen Unit 1 was completed on schedule in March 2009. This was soon followed by the placement of the first major structural module; the auxiliary building. As part of localization and the Peoples Republic of China (PRC) desire for self-reliance, a China-based module factory is constructing the major modules and manufacturing the containment vessel plates. The fabrication and welding of the containment vessel bottom head for Sanmen Unit 1 is now complete. The 2010 milestones for Sanmen Unit 1 include the setting of major modules such as the reactor vessel cavity, the steam generator, and refueling canal modules, plus containment vessel rings 1, 2, 3, and 4. All major equipment orders have been placed and the first deliveries are beginning to arrive. The technology transfer is also well underway. The Haiyang Unit 1 basemat was placed on schedule in September 2009 and Sanmen Unit 2 Nuclear Island (NI) concrete basemat placement was completed a month earlier than the milestone date of January 2010. Sanmen Unit 1 will be fully operational in November 2013 followed by Haiyang Unit 1 in May 2014. Operational dates for Sanmen Unit 2 and Haiyang Unit 2 are September 2014 and March 2015, respectively. As one of the world’s largest consumers of energy, China’s path in achieving sustainable energy has profound global economic and environmental consequences. The contract with the Westinghouse and Shaw Consortium for four AP1000 units is the largest of its type between the People’s Republic of China and the United States.
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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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Higo, Eishiro, Shota Soga, and Hiromichi Miura. "Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases." 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/icone2020-16819.

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Abstract This study provides an inter-unit common cause failure (CCF) analysis method utilizing the international CCF database. The inter-unit CCF is one of the possible major risks at a site with multiple units. The conventional CCF analysis is based on the CCF database, in which inter-unit CCF events rarely occur in real nuclear power plants. The conventional approach cannot be directly applied to inter-unit CCF cases because of the lack of data. The method ignores the asymmetricity among units, so it may lead to overly conservative outcomes if it is applied to inter-unit CCF. We have proposed a new concept, “commonality factor,” which represents the degree of similarity among components in different units and showed a concept that the inter-unit CCF probability can be expressed in terms of the intra-unit CCF probability with the commonality factor. The commonality factor is approximated based on CCF coupling factors, which tie two or more failures together as a CCF. This study explains how to estimate the commonality factor by analyzing the conventional CCF database and judging commonality among components from different units. The proposed method is demonstrated through two preliminary examples.
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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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Zhang, Sai, and Zhegang Ma. "Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment." 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/icone2020-16889.

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Abstract The catastrophic Fukushima nuclear accident reminded the nuclear community about potential extreme accident scenarios, including those involving multiple reactor units on the same site. In response to the Fukushima accident, the nuclear power industry developed and implemented a series of strategies, including Diverse and Flexible Coping Strategies (FLEX), to enhance the capacities of nuclear power plants (NPPs) to cope with extreme accidents. This study examines the impact of FLEX strategies on the overall risk from all reactor units located at the same NPP site, including risks from accidents involving either a single unit or multiple units. The fundamental, methodological element of this study is Multi-Unit Probabilistic Risk Assessment (MUPRA) requiring a shift in Probabilistic Risk Assessment (PRA) from a one-reactor-at-a-time mindset to a consideration of all reactors sharing a site. An integrated modeling approach for multi-unit event sequence development is leveraged to develop the MUPRA model and address intra-unit and inter-unit dependencies. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), a PRA software developed and maintained by Idaho National Laboratory for the United States (U.S.) Nuclear Regulatory Commission, serves as the platform for MUPRA modeling. This study selects loss of offsite power (LOOP) as a representative initiating event potentially occurring on a generic two-unit NPP site and impacting both reactor units. First, an MUPRA model, including multi-unit event trees, is developed to obtain single-unit and multi-unit accident scenarios. Next, different FLEX strategies are assumed; for example, whether FLEX equipment for multiple units can be used in a cross-connected manner. Lastly, the effectiveness of each postulated FLEX strategy is evaluated by incorporating the corresponding FLEX equipment and deployment logic into the MUPRA model.
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Allen, Wayne, David Anderson, and Bert Mayer. "Pickering B Nuclear Power Generating Station Condenser Performance Improvement." In 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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Ge, Fuchao, Yi Lin, Yuntao Ju, and Zhinan Qi. "Unit commitment considering the characteristics of nuclear and wind power." In 2018 International Conference on Power System Technology (POWERCON). IEEE, 2018. http://dx.doi.org/10.1109/powercon.2018.8602098.

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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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Kautzmann, David E., and Robert A. Ransom. "A Method for Estimating Moisture Separator Effectiveness on a Reheat Nuclear Unit." In ASME 2006 Power Conference. ASMEDC, 2006. http://dx.doi.org/10.1115/power2006-88232.

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Having a better understanding of the level of moisture separator performance is an important component in evaluating the cost benefit of a turbine or MSR improvement or retrofit. The documented methods of determining Moisture Separator Effectiveness (MS η) on a reheat nuclear cycle require extensive station instrumentation, which may not be available in many power plants, or the introduction of radioactive (or other) tracers into the plant system. Because of these difficulties and associated costs, moisture separator performance is typically not adequately evaluated or monitored. This situation can lead to significant misconceptions about the actual operating moisture separator effectiveness. Using data from field tests of multiple GE-designed horizontal moisture separators, important relationships between MS performance and certain operating parameters were established that form the basis of this proposed Moisture Separator test method. This test method is specifically designed to remove many of the known difficulties associated with the current testing methods while maintaining reasonable accuracy levels. By removing many of the roadblocks in testing moisture separators, MS η can now be calculated on a regular basis and will allow for periodic performance monitoring and performance degradation detection.
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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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Reports on the topic "Nuclear power unit"

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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GREENE, G. A., and 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), August 1998. http://dx.doi.org/10.2172/760987.

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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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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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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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Vo, T., B. Gore, F. Simonen, and S. Doctor. A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station. Office of Scientific and Technical Information (OSTI), August 1994. http://dx.doi.org/10.2172/10178938.

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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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Vo, T. V., H. K. Phan, B. F. Gore, F. A. Simonen, and S. R. Doctor. A pilot application of risk-informed methods to establish inservice inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station. Revision 1. Office of Scientific and Technical Information (OSTI), February 1997. http://dx.doi.org/10.2172/446366.

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9

JOINT BASE CHARLESTON SC. Environmental Assessment for Facilities Expansion at Naval Nuclear Power Training Unit -Charleston (NPTU Charleston), Joint Base Charleston, South Carolina. Fort Belvoir, VA: Defense Technical Information Center, September 2012. http://dx.doi.org/10.21236/ada627463.

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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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