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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.
Повний текст джерелаАнотація:
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.
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.
Повний текст джерела
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.
Повний текст джерелаАнотація:
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.
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.
Повний текст джерелаАнотація:
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.
5
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.
Повний текст джерелаАнотація:
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.
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.
Повний текст джерелаАнотація:
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.
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.
Повний текст джерелаАнотація:
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.
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.
Повний текст джерелаАнотація:
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.
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.
Повний текст джерелаАнотація:
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.
10
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.
Повний текст джерелаАнотація:
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.
11
Myslíková, Veronika. "Rizika spojená se zapojením jednotek sboru dobrovolných hasičů obcí do monitorování radiační situace." Master's thesis, Vysoké učení technické v Brně. Ústav soudního inženýrství, 2020. http://www.nusl.cz/ntk/nusl-414185.
Повний текст джерелаАнотація:
This diploma thesis focuses on the analyzing the current state of monitoring the radiation situation by volunteer firefighters units in the emergency planning area in Dukovany nuclear power plant surroundings. The process of measurement is divided into preparation for radiation leakage and application of learned procedures in the case of the occurred radiation leakage. The aim is to identify the dangers in the current process as well as the possible risks in the case of radiation emergency by risk analysis. Based on this analysis, improvements suggestions will be made. These measures will be evaluated by their applicability and their economic value. The system of monitoring by voluntary firefighters will be compared with another monitoring system, which can be also used. The result of the analysis will be a more effective way of monitoring, including safety of the firefighter and less financial complexity.
12
Moreno, Roman Miguel 1963. "Exergoeconomic analysis of a nuclear power plant." Diss., The University of Arizona, 1997. http://hdl.handle.net/10150/288727.
Повний текст джерелаАнотація:
Exergoeconomic analysis of a nuclear power plant is a focus of this dissertation. Specifically, the performance of the Palo Verde Nuclear Power Plant in Arizona is examined. The analysis combines thermodynamic second law exergy analysis with economics in order to assign costs to the loss and destruction of exergy. This work was done entirely with an interacting spreadsheets notebook. The procedures are to first determine conventional energy flow, where the thermodynamic stream state points are calculated automatically. Exergy flow is then evaluated along with destruction and losses. The capital cost and fixed investment rate used for the economics do not apply specifically to the Palo Verde Plant. Exergy costing is done next involving the solution of about 90 equations by matrix inversion. Finally, the analysis assigns cost to the exergy destruction and losses in each component. In this work, the cost of electricity (exergy), including capital cost, leaving the generator came to 38,400 $/hr. The major exergy destruction occurs in the reactor where fission energy transfer is limited by the maximum permissible clad temperature. Exergy destruction costs were: reactor--18,207 $/hr, the low pressure turbine--2,000 $/hr, the condenser--1,700 $/hr, the steam generator--1,200 $/hr. The inclusion of capital cost and O&M are important in new system design assessments. When investigating operational performance, however, these are sunk costs; only fuel cost needs to be considered. The application of a case study is included based on a real modification instituted at Palo Verde to reduce corrosion steam generator problems; the pressure in the steam generator was reduced from 1072 to 980 psi. Exergy destruction costs increased in the low pressure turbine and in the steam generator, but decreased in the reactor vessel and the condenser. The dissertation demonstrates the procedures and tools required for exergoeconomic analysis whether in the evaluation of a new nuclear reactor system concept, or in the assessment of the economic performance in operating plants.
13
Bertilsson, Richard. "Information Inadequacy in Nuclear Power Plant Accidents." Thesis, Linnéuniversitetet, Institutionen för informatik (IK), 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:lnu:diva-34390.
Повний текст джерелаАнотація:
The aim of this study is to compare the cause of the, to date, three onlycommercial nuclear power plant accidents. These are very complex incidents,which have dire impact on society and the environment and therefore benefitfrom further investigation, if there lays a possibility of identifying factors thatcould prevent further accidents in the future. In order to investigate this theactions and decisions that lead up to each nuclear meltdown was identified andcompared.The investigation was based on a qualitative study on three cases of nuclearmeltdown accidents. They are based on text analysis of official reports anddocumentaries on the subject. The theoretical background for this study wasKajtazi’s (2011) work on Information Inadequacy. The study was limited to theevents leading up to the accidents and do not include activities afterwards.The study shows that each case had different underlying reasons. It alsoshows that we seem to have learned something from our previous mistakes, andacted on them accordingly. From the Fukushima Daiichi accident we canrecommend that organizations in charge should take early warnings seriouslyand act upon them as soon as they are presented.
14
Simola, Kaisa. "Reliability methods in nuclear power plant ageing management /." Espoo [Finland] : Technical Research Centre of Finland, 1999. http://www.vtt.fi/inf/pdf/publications/1999/P379.pdf.
Повний текст джерела
15
Van, der Helm Mark Johan 1972. "Power plant degradation : a modular secondary plant and integral flow accelerated corrosion model." Thesis, Massachusetts Institute of Technology, 2000. http://hdl.handle.net/1721.1/8867.
Повний текст джерелаАнотація:
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2001.Includes bibliographical references (leaves 198-204).
Flow Accelerated Corrosion (FAC) is the most prevalent material degradation mechanism for low carbon steel in steam-water flow systems. The band of uncertainty in predictions of wear rate due to FAC spans one to two orders of magnitude. Such a wide range of uncertainty inhibits the ability to devise safe and economical repair and replacement schedules. The goal of this thesis is to reduce uncertainty of predictions of wear caused by FAC. Reduction in the uncertainty in FAC wear rate predictions is achieved through the development of a new predictive FAC model, the incorporation of this model in a flow system analysis environment, and the use of this environment to identify improved methodologies for predicting FAC wear rate. The new FAC model is based on a published empirical model, published data, and physical mechanisms identified to be significant in the wear process. The new FAC model is shown to have less uncertainty for single phase lab data and single and two phase plant data. The flow system analysis environment is an interactive program that calculates parameters relevant to the FAC phenomenon based on plant description. Functionality of this environment is validated for each of the four calculations it performs: thermodynamic, thermal hydraulic, chemistry, and degradation rate. Additionally, this environment can be used to analyze contributions to uncertainty that are not yet identified. This environment was used to analyze the contribution to uncertainty from the current method of incorporating chemistry parameters in predictions of FAC wear. Based on this analysis, suggestions are made to improve these methods, thereby reducing prediction uncertainty and improving the knowledge necessary for safer and more economical plant operation.
by Mark Johan van der Helm.
Ph.D.
16
Poston, Charles Thomas. "Nuclear power plant systems and security a graduate engineering course /." Diss., Columbia, Mo. : University of Missouri-Columbia, 2008. http://hdl.handle.net/10355/5789.
Повний текст джерелаАнотація:
Thesis (M.S.)--University of Missouri-Columbia, 2008.The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on September 12, 2008) Includes bibliographical references.
17
Jalel, Nameer Adnan. "Fault diagnosis and accident analysis in nuclear power plant." Thesis, University of Sheffield, 1991. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.335950.
Повний текст джерела
18
McHenry, Robert Sean. "Nuclear power plant surveillance issues for extended operating cycles." Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/43343.
Повний текст джерела
19
Li, Feng 1968 October 24. "Efficient investment allocation for improving nuclear power plant performance." Thesis, Massachusetts Institute of Technology, 1999. http://hdl.handle.net/1721.1/85316.
Повний текст джерела
20
Strother, Matthew Brian. "Hydrodynamic analysis of the offshore floating nuclear power plant." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/100112.
Повний текст джерелаАнотація:
Thesis: Nav. E., Massachusetts Institute of Technology, Department of Mechanical Engineering, 2015.Thesis: S.M. in Engineering and Management, Massachusetts Institute of Technology, Engineering Systems Division, 2015.
Cataloged from PDF version of thesis.
Includes bibliographical references (pages 85-86).
Hydrodynamic analysis of two models of the Offshore Floating Nuclear Plant [91 was conducted. The OFNP-300 and the OFNP-1100 were both exposed to computer simulated sea states in the computer program OrcaFlex: first to sets of monochromatic waves, each consisting of a single frequency and waveheight, and then to Bretschneider and JONSWAP spectra simulating 100-year storms in, respectively, the Gulf of Mexico and the North Sea. Hydrodynamic coefficients for these simulations were obtained using a separate computer program, WAMIT. Both models exhibited satisfactory performance in both heave and pitch. An alternative design of the OFNP-300 was developed and similarly analyzed in attempt to further improve hydrodynamic performance. A catenary mooring system was designed and analyzed for both plant models. The number of chains and the length of each were selected to ensure the mooring systems would withstand, with sufficient margins of safety, the maximum tension produced in a 100-year storm. This analysis was conducted both with all the designed mooring lines intact, and with the worst-case line broken. A lifecycle cost analysis of various mooring systems was conducted in order to minimize the cost of the mooring system while maintaining adequate performance.
by Matthew Brian Strother.
Nav. E.
S.M. in Engineering and Management
21
Jaliff, Juan O. (Juan Omar). "Organization and management characteristics of a nuclear power plant." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/13818.
Повний текст джерела
22
McGhee, Sean A. "Quantifying the Societal Risks of Nuclear Power Plant Accidents." The Ohio State University, 2013. http://rave.ohiolink.edu/etdc/view?acc_num=osu1366035332.
Повний текст джерела
23
Liu, Haiyong 1972. "An experimental investigation of a passive cooling unit for nuclear plant containment." Thesis, Massachusetts Institute of Technology, 1999. http://hdl.handle.net/1721.1/85273.
Повний текст джерелаАнотація:
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering; and, (S.M.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1999.Includes bibliographical references (leaves 84-86).
by Haiyang Liu.
S.M.
24
Peters, Kenneth John. "A reliability program for nuclear power plant emergency diesel generators." Master's thesis, This resource online, 1990. http://scholar.lib.vt.edu/theses/available/etd-02162010-020015/.
Повний текст джерела
25
Lapp, Christopher Warren. "A methodology for modular nuclear power plant design and construction." Thesis, Massachusetts Institute of Technology, 1989. http://hdl.handle.net/1721.1/96442.
Повний текст джерела
26
Boesak, Dawid John Johannes. "Voltage stability analysis of a power system network comprising a nuclear power plant." Master's thesis, Faculty of Engineering and the Built Environment, 2018. http://hdl.handle.net/11427/30056.
Повний текст джерелаАнотація:
As recently as 2016, the performance of South Africa’s power utility has shown that it is not resilient enough to withstand the consequences of a power system blackout. Blackouts are defined as being a form of power system instability that can be brought about by a variety of abnormal network scenarios. The most common modes of failure are grouped under the term power system stability. In this dissertation, the different modes of power stability that can affect a nuclear power station will be investigated and discussed. The particular phenomenon that will be focused on, however, is the effect that voltage instability has on the ability of generators and loads to perform their standard functions, thus ensuring a secure power system. To investigate the effect that voltage instability has on a nuclear power station, this dissertation will look at relevant literature on the topic. In addition, by extracting from common examples of national and international occurrences of voltage stability, this dissertation will record the effects that this phenomenon has on the security of a power system, in particular on nuclear power plants. To model the network containing a nuclear power plant for the evaluation of voltage stability, the different mathematical models of the generation plant are presented, which include: the automatic voltage regulator, power system stabilizer, governor, nuclear reactor, and excitation system. Also presented are mathematical models of network equipment such as under voltage tap changers and the dynamic loads that are of interest when evaluating voltage stability. The models used for evaluation of the voltage stability phenomenon affecting a nuclear power plant and the surrounding integrated power system are built in the Digsilent PowerFactory® software. The scenario for evaluation is based on a voltage stability event that occurred around at the Koeberg nuclear power system situated in the Western Cape province on South Africa on 15 October 2003. It is commonly accepted that voltage stability can be evaluated at a steady state level by performing power versus voltage (PV) analysis to determine the voltage buses vulnerable to voltage collapse, and reactive power versus voltage (QV) analysis to determine the critical reactive devices required to avert a voltage instability event. The scenarios that are evaluated for voltage stability are divided into two sections: i) a PV and QV analysis as per the event that occurred on 15 October 2003 and ii) present-day voltage stability indices for PV and QV if mixed with a generation such as renewable energy sources that include wind, solar, biomass and concentrated solar power (CSPs). The result reveals the vulnerabilities of the nuclear power plant and the surrounding integrated power system due to a voltage instability event. Some of the solutions proposed include a review of the typical power system protection schemes — such as under and overvoltage detection scheme — that are used. In the study, PV and QV curves provide v good indications of the state of critical busbars and the reactive power reserve margins available before instability can potentially settle in. Simulations confirmed the effectiveness of critical equipment installed in the Western Grid and the effect on their electrical parameters such as torque and the slip on motors.
27
Guyer, Brittany (Brittany Leigh). "Nuclear power plant performance assessment pertaining to plant aging in France and the United States." Thesis, Massachusetts Institute of Technology, 2013. http://hdl.handle.net/1721.1/82452.
Повний текст джерелаАнотація:
Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013.Cataloged from PDF version of thesis.
Includes bibliographical references (pages 171-174).
The effect of aging on nuclear power plant performance has come under increased scrutiny in recent years. The approaches used to make an assessment of this effect strongly influence the economics of nuclear power plant operation. This work aims (a) to determine how the risk-informed approach to performance assessment can be specifically improved, (b) to formulate and demonstrate a method for risk-informed nuclear power plant component reliability analysis, and (c) to assess the applicability of these improvements to the nuclear regulatory environments of the United States and France, the countries having the largest national nuclear power programs. In order to address the first objective, a case study of the U.S. and French regulatory treatment of the pressurized thermal shock phenomenon was performed. A new methodology that can be applied to the construction of risk-informed analyses was developed in response to the findings of the case study. The methodology specifically aims to improve upon current risk-informed methods, which implement a hybrid of best-estimate and conservative modeling, by increasing the use of risk-based modeling justification in order to allow for the development of a more logically consistent analysis. The second objective is addressed through the development of a new reliability model describing the effects of transient-induced degradation. The reliability model is applied through the demonstration of a risk-informed method for the calculation of fatigue degradation. The data requirements for the future successful implementation of this risk-informed method are presented. Examining the applicability of the risk-informed approach to U.S. and French nuclear power plant regulation showed that currently the U.S. is a more progressive implementer of risk-informed practices. This examination revealed, however, than an alternative approach known as the best-estimate plus uncertainty (BEPU) method could be considered for application in regulatory environments, such as in France, that are less accepting of the risk-informed approach. In order to understand how the BEPU method could be improved, the U.S. approach to BEPU was analyzed and recommendations for its future application are presented.
by Brittany L. Guyer.
Sc.D.
28
Gagliani, Roberto. "Distributed capacitance sensing for characterization of nuclear power plant cables." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2018.
Знайти повний текст джерелаАнотація:
Depending on their location in a nuclear power plant, cables are exposed to mechanical stresses, elevated temperature, radiation, humidity and environmental stresses which can lead the cables to an earlier degradation if not well designed. For this reason, it is crucial to understand how materials that insulation and jacket are made of, installed in NPPs, will age during their service life and to develop condition monitoring techniques to assure continued safe operation under the normal operating condition and under Design Basis Event (DBE). Nowadays methods based on tensile tests like Elongation at Break (EaB) are the most used as condition monitoring technique since their direct correlation with the ageing effect. However, these destructive methods consist in the destruction of the cables and their replacement in their initial position which means a decrease of reliability of the entire system. Non-destructive techniques such as Dielectric Spectroscopy (DS) are showing good correlation with ageing. In this work, DS on a three-conductor long cable with a thermally-aged middle section is carried out. Starting with measurements of the electrical properties of a pristine cable and the same type of cable with the aged section for a first preliminary assessment, the latter is made successively shorter and the variation of the capacitance (here considered as specific capacitance, pF/m) and dissipation factor are studied with the increase in Damage Ratio (R), the ratio between the length of the damaged section and the total length of the cable. The goal is to figure out if it is possible to detect ageing effect by measuring electrical properties of the pristine section of the same cable, i.e. if the DS can distinguish between a pristine cable and the same cable containing a middle thermally-aged section.
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Jurewicz, Jacob M. "Design and construction of an offshore floating nuclear power plant." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/103707.
Повний текст джерелаАнотація:
Thesis: S.M. and S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015.Cataloged from PDF version of thesis.
Includes bibliographical references (pages 135-138).
This thesis details the ongoing development of a new Offshore Floating Nuclear Plant (OFNP) concept that exhibits a promising potential for economic and rapid deployment on a global scale. The OFNP creatively combines state-of-the-art Light Water Reactors (LWRs) and floating platforms similar to those used in offshore oil and gas operations. A reliable and cost-effective global supply chain exists for both technologies, which enables a robust expansion in the use of nuclear energy on a time scale consistent with combating climate change in the near future. The OFNP is a plant that can be entirely built within a floating platform in a shipyard, transferred to the site, where it is anchored within 12 nautical miles (22 km) off the coast in relatively deep water (=/> 100 m), and connected to the grid via submarine AC transmission cables. Shipyard construction ensures a supply of qualified workers and facilities, and it brings mass-production-like construction efficiency to existing reactor designs. Eventual shipyard decommissioning allows sites to immediately return to a "green field" condition when the plant's life is spent. The crews would operate in monthly or semi-monthly shifts with onboard living quarters, similar to oil and gas platforms. The OFNP is a nuclear plant specifically designed for the global market: it can be constructed in one country or multiple countries and exported internationally. It lends itself to a flexible and mobile electricity generation strategy, which minimizes the need for indigenous nuclear infrastructure in the host country and does not commit the customer to a 40 to 60 years-long project.
by Jacob M. Jurewicz.
S.M. and S.B.
30
DeVita-Cochrane, Cynthia Catherine. "Personality Factors and Nuclear Power Plant Operators: Initial License Success." ScholarWorks, 2015. https://scholarworks.waldenu.edu/dissertations/1884.
Повний текст джерелаАнотація:
Commercial nuclear power utilities are under pressure to effectively recruit and retain licensed reactor operators in light of poor candidate training completion rates and recent candidate failures on the Nuclear Regulatory Commission (NRC) license exam. One candidate failure can cost a utility over $400,000, making the successful licensing of new operators a critical path to operational excellence. This study was designed to discover if the NEO-PI-3, a 5-factor measure of personality, could improve selection in nuclear utilities by identifying personality factors that predict license candidate success. Two large U.S. commercial nuclear power corporations provided potential participant contact information and candidate results on the 2014 NRC exam from their nuclear power units nation-wide. License candidates who participated (n = 75) completed the NEO-PI-3 personality test and results were compared to 3 outcomes on the NRC exam: written exam, simulated operating exam, and overall exam result. Significant correlations were found between several personality factors and both written and operating exam outcomes on the NRC exam. Further, a regression analysis indicated that personality factors, particularly Conscientiousness, predicted simulated operating exam scores. The results of this study may be used to support the use of the NEO-PI-3 to improve operator selection as an addition to the current selection protocol. Positive social change implications from this study include support for the use of a personality measure by utilities to improve their return-on-investment in candidates and by individual candidates to avoid career failures. The results of this study may also positively impact the public by supporting the safe and reliable operation of commercial nuclear power utilities in the United States.
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Uwizerimana, Salome. "Structural Modeling and Dynamic Analysis of Nuclear Power Plant Structures." The Ohio State University, 2015. http://rave.ohiolink.edu/etdc/view?acc_num=osu1449489161.
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Mattmuller, Adam. "Nuclear Power Plant Maintenance Improvement via Implementation of Wearable Technology." The Ohio State University, 2016. http://rave.ohiolink.edu/etdc/view?acc_num=osu1461760209.
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Langaas, Gjertrud Louise. "Measurements of radioactivity in plant and soil samples taken near a nuclear power plant." Thesis, Uppsala universitet, Institutionen för teknikvetenskaper, 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-296371.
Повний текст джерелаАнотація:
This project is a study of six soil and vegetation samples taken near the nuclear power plant at Ringhals, Sweden. The purpose was to detect any signs of radioactivity in the soil and vegetation originating from the plant, while simultaneously giving insight on the advantages and limitations of using equipment from the radioecology lab at the Swedish University of Agricultural Sciences. The samples were examined by a high purity germanium detector, and the resulting spectra were analyzed in Matlab. Besides Cs-137 from the Chernobyl accident and from atomic bomb tests the study found no proof of radioactivity derived from nuclear power waste or emissions. The results from the analysis were compared with the automatic software Apex-Gamma. In general there was a good agreement between the two methods, with discrepancies never larger than a factor of two. An improvement of the accuracy can be obtained through longer measurement times, and analysis of each spectra separately before the subtraction of the background contribution.
34
Turek, Michael Gerald. "System dynamics analysis of financial factors in nuclear power plant operations." Thesis, Massachusetts Institute of Technology, 1995. http://hdl.handle.net/1721.1/37007.
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35
Tengberg, Oskar. "Implementation of Hydro Power Plant Optimization for Operation and Production Planning." Thesis, Luleå tekniska universitet, Institutionen för teknikvetenskap och matematik, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:ltu:diva-74274.
Повний текст джерелаАнотація:
Output power of hydro power plant was modelled and an optimization algorithm was implemented in a tool for optimizing hydro power plants. The tool maximizes power output of a hydro power plant by distributing water over a set of active units in the power plant which will be used in planning of electricity production. This tool was built in a MATLAB environment, using the optimization toolbox, and a GUI was developed for Vattenfall. The optimization tool was based on the same architecture as the current tool used for this kind of optimization which is to be replaced by the work presented in this thesis. Therefore, the goal was to achieve the same optimal results as the current optimization tool. Power output of three of Vattenfall’s hydro power plants were computed and two of these plants were optimized. These power output results were compared to results from the optimization tool currently used. This showed differences within the inaccuracy of measurements of ≤ 0.3%. These three power plants proved that the new tool is sufficient to replace the current tool but further testing is recommended to be conducted on more of Vattenfall’s hydro power plants to prove its consistency.
36
Hassan, Mohamed Elhafiz. "Power Plant Operation Optimization : Unit Commitment of Combined Cycle Power Plants Using Machine Learning and MILP." Thesis, mohamed-ahmed@siemens.com, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-395304.
Повний текст джерелаАнотація:
In modern days electric power systems, the penetration of renewable resources and the introduction of free market principles have led to new challenges facing the power producers and regulators. Renewable production is intermittent which leads to fluctuations in the grid and requires more control for regulators, and the free market principle raises the challenge for power plant producers to operate their plants in the most profitable way given the fluctuating prices. Those problems are addressed in the literature as the Economic Dispatch, and they have been discussed from both regulator and producer view points. Combined Cycle Power plants have the privileges of being dispatchable very fast and with low cost which put them as a primary solution to power disturbance in grid, this fast dispatch-ability also allows them to exploit price changes very efficiently to maximize their profit, and this sheds the light on the importance of prices forecasting as an input for the profit optimization of power plants. In this project, an integrated solution is introduced to optimize the dispatch of combined cycle power plants that are bidding for electricity markets, the solution is composed of two models, the forecasting model and the optimization model. The forecasting model is flexible enough to forecast electricity and fuel prices for different markets and with different forecasting horizons. Machine learning algorithms were used to build and validate the model, and data from different countries were used to test the model. The optimization model incorporates the forecasting model outputs as inputs parameters, and uses other parameters and constraints from the operating conditions of the power plant as well as the market in which the plant is selling. The power plant in this mode is assumed to satisfy different demands, each of these demands have corresponding electricity price and cost of energy not served. The model decides which units to be dispatched at each time stamp to give out the maximum profit given all these constraints, it also decides whether to satisfy all the demands or not producing part of each of them.
37
Villemin, Maxime. "Alarm handling in the control room of a Nuclear Power Plant." Thesis, KTH, Fysik, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-92111.
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Walden, Robert P. "A study of nuclear power plant construction in the United States." Thesis, Monterey, California. Naval Postgraduate School, 1991. http://hdl.handle.net/10945/26276.
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Chu, Xinyuan. "System dynamics modeling for human performance in nuclear power plant operation." Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41297.
Повний текст джерелаАнотація:
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.Includes bibliographical references (p. 62).
Perfect plant operation with high safety and economic performance is based on both good physical design and successful organization. However, in comparison with the affection that has been paid to technology research, the effort that has been exerted to enhance NPP management and organization, namely human performance, seems pale and insufficient. There is a need to identify and assess aspects of human performance that are predictive of plant safety and performance and to develop models and measures of these performance aspects that can be used for operation policy evaluation, problem diagnosis, and risk-informed regulation. The challenge of this research is that: an NPP is a system that is comprised of human and physics subsystems. Every human department includes different functional workers, supervisors, and managers; while every physical component can be in normal status, failure status, or a being-repaired status. Thus, an NPP's situation can be expressed as a time-dependent function of the interactions among a large number of system elements. The interactions between these components are often non-linear and coupled, sometime there are direct or indirect, negative or positive feedbacks, and hence a small interference input either can be suppressed or can be amplified and may result in a severe accident finally. This research expanded ORSIM (Nuclear Power Plant Operations and Risk Simulator) model, which is a quantitative computer model built by system dynamics methodology, on human reliability aspect and used it to predict the dynamic behavior of NPP human performance, analyze the contribution of a single operation activity to the plant performance under different circumstances, diagnose and prevent fault triggers from the operational point of view, and identify good experience and policies in the operation of NPPs.
(cont.) Regarding the human reliability analysis function, the partial Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method was applied. Performance Shaping Factors (PSFs) were employed to analyze the influence of human performance indicators already existing in ORSIM. Based on the human performance model, an operation case study was investigated. A series of carefully chosen candidate policies were tested on a computerized model that represents the structure, processes, and interactions of the underlying target NPP systems. These candidates included: (1) New management system application; (2) Personnel population change, (3) Planning delay, and (4) Tolerance to surprise workload.
by Xinyuan Chu.
S.M.
40
Biegel, Kathryn E. "Scenario modeling for feasibility assessment of nuclear power plant construction projects." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/103714.
Повний текст джерелаАнотація:
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015."June 2015." Cataloged from PDF version of thesis.
Includes bibliographical references (pages 44-47).
In historical and current experience, the economics of nuclear power have proven to be problematic for utility companies. Construction costs and schedules have proven to be highly unpredictable, with the average reactor construction project costing two to three times more than its initial budget and taking almost twice as long to complete as expected. The causes of this phenomenon have not been well-characterized, even two decades after the last new reactor was brought online in 1996. Scenario generation can provide useful information about the economic viability of nuclear construction projects over a variety of parameter spaces without having to make prescriptive assertions about likely single values for delay and other difficult-to-predict parameters. The MEERKAT model creates scenarios over two different reactor types (Westinghouse AP1000 and NuScale SMR plant); three delay cases (optimistic, median, and pessimistic based on historical data); and six different utility company credit ratings (which translate into varying costs of capital). MEERKAT outputs the levelized cost of electricity (LCOE) for each scenario and compares them to average electricity prices for a number of regions in the United States. These scenarios produce levelized costs of electricity (LCOEs) that are not competitive in a deregulated market in any case, and which may be competitive in regulated markets under certain optimistic conditions. If the AP1000 is considered as more credit-stressful than the SMR project, the SMR becomes more competitive with the AP1000, but the projects' viability in the wider market remains unchanged. However, in general terms the smaller up-front cost of the SMR makes it a more feasible endeavor for a wider variety of utility companies, increasing the potential customer base for nuclear power generation units.
by Kathryn E. Biegel.
S.B.
41
Ellison, James F. (James Frederick). "Modeling nuclear power plant maintenance : promoting new discussion and better policy." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/38763.
Повний текст джерелаАнотація:
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Political Science, 1996, and Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1995.Includes bibliographical references (p. 101).
by James F. Ellison, Jr.
M.S.
42
Ou, Yan-Zhen, and 歐彥蓁. "A Study of Packing Problems for the Decommissioning Nuclear Power Plant Unit." Thesis, 2018. http://ndltd.ncl.edu.tw/handle/42v9q4.
Повний текст джерелаАнотація:
碩士國立臺北科技大學
經營管理系碩士班
106
This study mainly investigates the three-dimensional packaging problem for the decommissioning nuclear power plant unit. The constraints include active conditions and weight limitations of the given containers. The objective is to minimize the number of given containers to reduce the storage space and costs. To ensure the safety and smoothness of decommissioning work of nuclear facilities and to find out the optimal spatial configuration, this study explores the heuristic algorithms and deterministic algorithms for placing dismantling units to improve space utilization rate. The proposed method can effectively solve the problem to reduce the packing cost. Several numerical examples are presented to illustrate the effectiveness and efficiency of the proposed method.
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Li, Wei Ting, and 李煒婷. "Analysis of Unit 3 Fukushima Nuclear Power Plant Accident Using MELCOR 1.8.5 Code." Thesis, 2014. http://ndltd.ncl.edu.tw/handle/57551607601920012295.
Повний текст джерелаАнотація:
碩士國立清華大學
核子工程與科學研究所
102
On 2011 March 11, a strong earthquake induced several large waves of tsunami hit the east coast of Japan. The tsunami caused extensive damage to the site of Fukushima Daiich Nuclear Power Plant (NPP). Fukushima Daiichi NPP employed BRW4 reactor with MARK I containment, which is identical to the design of Chinshan NPP of Taiwan Power Company. In the present study, an input deck of MELCOR based on the design of Chinshan NPP is construct to simulate the Fukushima Daiichi Unit 3 accident. In the simulation, the timings of water injection, depressurization, and containment venting are set as specified in the official Japanese government report about the accident. The results of simulation demonstrate that the hydrogen burns observed during the accident are not predicted by the code. The the reactor pressure vessel and the containment are remain intact throughout the accident. As predicted in the MELCOR simulation, there is 67 kilogram of hydrogen leak into the reactor building. Nevertheless, the concentration of hydrogen is still too low to induce hydrogen burn. There is no radionuclide release to environment in the base case simulation due to that the reactor building is kept intact up to the end of the simulation. In a sensitivity study, it is assumed that the reactor building breaches at the time specified in the official government report, The results show that 1.3% of Xe is released to the environment. The releases of other radionuclides are very minor. The results of MELCORE simulation of the accident are compared with the results of MAAP5 simulation. The differences are very significant. The results of MAAP5 simulation indicated that the reactor building breached due to the pressure spike predicted at 68.2 hours after scram, which was caused by the relocation of molten core from core region into vessel lower plenum.
44
Guo, Hong-yang, and 郭浤洋. "A Study on the Pumped Storage Unit Dispatching and Power System Stability after Commercial Operation of the Lungmen Nuclear Power Plant." Thesis, 2011. http://ndltd.ncl.edu.tw/handle/dpt9yx.
Повний текст джерелаАнотація:
碩士國立臺灣科技大學
電機工程系
99
As far as power system operation is concerned, it is very important to set up enough spinning reserve to avoid an unexpected generator breakdown and the lack of electricity which comes from load forecast error. Therefore, the power company must establish a set of planning principles to make sure that the power system is capable of running safely, supplying sufficient power, maintaining superior power quality and reducing the cost of electricity. Taiwan Power Company is expected to start commercial operation for the first unit of Lungmen nuclear power plant in 2012 and the second unit will start in 2013. The largest generator in the system will be Lungmen nuclear power plant whose rated capacity is 1350MW in place of Kuosheng nuclear power plant whose rated capacity is 985MW and the capacity will be increased nearly 40%. However, if Lungmen nuclear power plant has a power outage, it is possible to have under-frequency load shedding considered in a low load in winter during a year. This thesis uses the load-frequency sensitivity factor which was provided by Taiwan Power Company to calculate the lowest frequency of each period in winter when Lungmen nuclear power plant has a breakdown and to estimate whether there is the possibility of having under-frequency load shedding or not. If it does, pumped storage units will be taken as instantaneous reserve therefore the reliability of power system can improve dramatically during this period. As a result, systems can reduce the arrangement of frequency regulating reserve and save the cost of electricity. This thesis also uses PSS/E simulation software to analyze the change of power flow after Lungmen nuclear power plant is incorporated into Taiwan Power System. When Lungmen nuclear power plant break down, firstly, the software will simulate the shift of system frequency and check whether the frequency regulating reserve is sufficient or not. Secondly, the change of power flow is analyzed after generators have been increased capacity. Finally, the reasonable unit commitment is suggested.
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Visagie, Herman. "Evaluation and verification of an architecture suitable for a multi-unit control room of a pebble bed high temperature reactor nuclear power plant / Herman Visagie." Thesis, 2015. http://hdl.handle.net/10394/15761.
Повний текст джерелаАнотація:
Current regulations specify the minimum number of operators required per nuclear power plant.
However, these requirements are based on the operation of large nuclear power plants, which
are not inherent safe and can result in a meltdown. For newly developed small nuclear
reactors, the current number of operators seems to be excessive causing the technology to be
less competitive. Before the number of required operators can be optimised, it should be
demonstrated that human errors will not endanger or cause risk to the plant or public.
For this study, a small pebble bed High Temperature Reactor (HTR) Nuclear Power Plant
(NPP), the Th-100, was evaluated. The inherent safety features of this type of nuclear reactor
include independent barriers for fission product capture and passive heat dissipation during a
loss of coolant. The control and instrumentation architecture include two independent
protection systems. The Control and Limitation System is the first protection system to react if
the reactor parameters exceed those of the normal operational safe zone. If the Control and
Limitation System fail to maintain the reactor within the safe zone, the Reactor Protection
System would at that time operate and force the reactor to a safe state. Both these automated
protection systems are installed in a control room local to the reactor building, protected from
adverse conditions. In addition, it is connected to a semi-remote control room, anticipated as a
multi-unit control room to include the monitoring and control of the auxiliary systems.
Probable case studies of human error associated with multi-unit control rooms were evaluated
against the logic of the Control and Limitation System. Fault Tree Analysis was used to
investigate all possible failures. The evaluation determined the reliability of the Control and
Limitation System and highlighted areas which design engineers should take into account if a
higher reliability is required. The scenario was expanded, applying the same methods, to
include the large release of fission products in order to verify the reliability calculations. The
probability of a large release of fission products compared with studies done on other nuclear
installations revealed to be much less for the evaluated HTR as was expected.
As the study has proved that human error cannot have a negative influence on the safety of the
reactor, it can be concluded that the first step has been met which is required, when applying for
a waiver to utilise a multi-unit control room for the small pebble bed HTR NPP. Also, from the
study, it is recommended that a practical approach be applied for the evaluation of operator
duties on a live plant, to optimise the number of operators required. This in turn will position the
inherent safe HTR competitively over other power stations.MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2015
46
林紋仕. "Stability analysis on a nuclear power plant during power." Thesis, 2006. http://ndltd.ncl.edu.tw/handle/74366397272903603357.
Повний текст джерелаАнотація:
碩士國立清華大學
工程與系統科學系
94
For a nuclear power plant (NPP), there are three power uprate levels: Measurement Uncertainty Recapture (MUR), Stretch Power Uprat (SPU), and Extended Power Uprate (EPU). The purpose of this study is to analyze the stability of a light water reactor which is under power uprate condition (MUR). In this study, we are focusing on the stability issue such as monitoring the status of a power uprated core and the precautions against the operation point entering the unstable region, etc. The computer code --- LAPUR5.2 is chosen as the tool for calculation. Based on the data from KuoSheng (Unit I) and ChinShan (Unit II) nuclear power plants, four operation points are calculated by LAPUR5.2 for assumed power uprate tasks. These simulation results are compared with the results from other U.S. NPPs which have successful experience in power uprate. Some stability problems which may take place in Taiwan’s NPP during the power uprate tasks are discussed in this study. The research results show that a limited power uprate (MUR), usually within 2% of the core power level, will not make the decay ratio exceed 0.8. In many simulation cases the decay ratio is much less than 0.8. Therefore, it is certain that MUR can hardly affect the stability of a nuclear power plant.
47
LI, YI-FANG, and 李宜芳. "Analysis and Improvement of Evacuation Procedures for Nuclear Power Plant Accident－A Case of Maanshan nuclear power plant." Thesis, 2013. http://ndltd.ncl.edu.tw/handle/unr9am.
Повний текст джерелаАнотація:
碩士中華大學
運輸科技與物流管理學系碩士班
101
The coast of large-scale 9.0 earthquake occurred at northeastern in Japan, at 14:46 11/03/ 2011, which was an about 40.1 m high tsunami, and fire and nuclear accident. In addition, resulted in local function paralysis and accident renewed a question about nuclear security in Taiwan. Although there are the public protective work and the emergency evacuation plan for the nuclear accident, the public lack a process of the nuclear accident evacuation in current internal nuclear accident. However, an authority is not clear enough to the nuclear safety operations. In this research, first, we studied the legislations of a nuclear accident, and clarified the responsibilities and norms on central government and local government. And then we looked back the relevant nuclear accident and nuclear accident operating procedures, which conduct analysis to find out trouble spots. According to nuclear power problem, the plant could be improved; In this study, we study deeply the students of the nuclear accident evacuation operating procedures. By interviewing with scholars and relevant units reviewed the research proposed nuclear power plant outside the plant operating procedures to evacuate peoples and students evacuation procedures at trouble spots and defects, according to recommendations given by scholars operating procedures on the amendment, the final conclusions recommendations.
48
Ling, Youn Cheng, and 林永振. "Nuclear Safety Analysis of severe accident of nuclear power plant." Thesis, 1996. http://ndltd.ncl.edu.tw/handle/26840051333231831177.
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49
Wang, Yi-ping, and 王逸萍. "Legislators’ Participation in Fourth Nuclear Power Plant." Thesis, 2013. http://ndltd.ncl.edu.tw/handle/72603645863956447305.
Повний текст джерелаАнотація:
碩士東吳大學
政治學系
101
This article explores the position and attitude of legislators whose constituency is used to be the location of Fourth Nuclear Power Plant. The study finds that the legislative participation of legislators in Taipei County can be analyzed by three stages. The first stage starts from 1st February 1990 to 26th October 2000. Before the DPP government announces the Fourth Nuclear Power Plant shutdown, the legislative participation of DPP legislators in Taipei County is much more aggressive than KMT legislators in the same county. The second stage starts from 27th October 2000 to 11th March 2011. After the Fourth Nuclear Power Plant was shut down and before 311 incident ago, the legislative participation of DPP and KMT legislators in Taipei County are much more passive than before. The third stage starts from 12th March 2011 to 12th April 2013. After 311 incident, DPP legislators in New Taipei City regain power coming from anti－nuke people, which makes their attitude become aggressive. But KMT legislators in New Taipei City seldom take part in the legislative participation still, and they go to vote for the bill of the Fourth Nuclear Power Plant in Legislative Yuan only when KMT do political mobilization.
50
Locke and 許振華. "The Argument of The Fourth Nuclear Power Plant." Thesis, 2001. http://ndltd.ncl.edu.tw/handle/13901313016636454758.
Повний текст джерелаАнотація:
碩士國立成功大學
政治經濟研究所
89
Abstract Since 1970s，It has been exceeding thirty years when Taiwan initiated the public basic construction of the nuclear power. Though it enhanced economic development and brought along change of industrial structure，it caused all walks of life to call in question the quality of safety and the quality of environment for the nuclear power，it would like whirlpool to lead into much impurity continuously and become more and more magnification. So，the development of the nuclear power，after the fourth nuclear power plant built in 1980，following up intervening strongly of political power and social power，they made the fourth nuclear power plant which its public controversy possessed the quality of science technology didn''t "de-politicized"，therefore；it missed the solve juncture to seek for the way of technological specialization. The Democrative Progress Party（DPP）Which flaunted "anti-nuclear" held power in 2000，it changed the budget bill of the fourth nuclear power plant，which had finished the executing and legislative process，caused the controversy to rrise again. Although the Executive Yuan declared the fourth nuclear power plant to build again，the controversy of the nuclear power still existed，it had never obtained the unanimous understanding of the ruling party and the opposite party and all people. It still leave foreshadowing of anti-nuclear plebiscite？What kind of appropriate nuclear power policy for our future policy in Taiwan？ Therefore, from the pointview of political economy, the purpose of this study is to investigate the relationship between the electricity construction and the energy development, on the development and argument of the fourth nuclear power plant. Four factors─ Politics & Society, Economics, Technology & Security, and Ecology & Environmental Protection─are used to discuss the two themes of this study─the argument of the fourth nuclear power plant and the development of nuclear power. It will be verified from the “State Theory” and the “Government-interfering Theory.” Chapter III is the discussion on the energy policy from the hydraulic and thermal electrogeneration to nuclear power. It also discusses the fourth nuclear power plant project from Chiang Ching-Kuo to Chen Shui-Bian; furthermore, it makes a “history-structure” analysis. Chapter IV illustrates the dispute of the fourth nuclear power plant, between the Executive Yuan and the Legislative Yuan. Then, it searches for a suitable theory to analyze the dispute. Chapter V will explore the electric power energy after the fourth nuclear power plant project, and evaluates the practicability of substitute program (it contains mainly the independent power plants, the reproducible energy, and the energy retrenchment.) Understanding the importance of nuclear power, the goal of nuclear power development is to promote an electric power policy balanced among industry, energy, and environmental protection. Chapter IV will review the argument and the substitute program of the fourth nuclear power plant. Furthermore, it proposes a conclusion and a prediction on the future of Taiwan’s nuclear power development, including the solution to the dispute, the prospect of electric power energy, the practicability of substitute program.