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Статті в журналах з теми "Nuclear power unit"

Автор: Grafiati

Опубліковано: 30 травня 2022

Оновлено: 31 травня 2022

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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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2

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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3

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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4

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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5

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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6

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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7

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

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8

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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Анотація:

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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9

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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10

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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11

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

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

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12

Yefimov, A., D. Kukhtin, T. Potanina, T. Harkusha, and V. Kavertsev. "Operational personnel decision-making supportautomatic system at nuclear power plant generating unitsby criterion of technical economic efficiency with dueconsideration of reliability factors." Nuclear and Radiation Safety, no. 2(78) (June 7, 2018): 11–19. http://dx.doi.org/10.32918/nrs.2018.2(78).02.

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Анотація:

New methods and approaches to development of nuclear power plant unit imitation models development. An imitation model is proposed for nuclear power plant unit developed on the basis of oriented graph applied to unit flow diagram description logic-numerical operators for calculation of parameters and characteristics determining its operation efficiency, reliability and safety. Automatic system is described developed on the basis of imitation model for decision-making support, applied to analysis of VVER nuclear power plant unit operation efficiency with due consideration of equipment operation reliability and safety indices.

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13

ONO, Yushi, Motonori NAKAGAMI, Haruhisa HAYASHI, and Yoshihiro ICHIKAWA. "Pipe Rupture Incident of Hamaoka Nuclear Power Station Unit-1." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 44, no. 11 (2002): 784–89. http://dx.doi.org/10.3327/jaesj.44.784.

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14

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

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15

KOBAYASHI, Masahide, Tadashi NARABAYASHI, Masashi TUJI, Go CHIBA, Yasunori NAGATA, and Tomohiro SHIMOE. "Accident Analysis of Fukushima Daiichi Nuclear Power Station Unit 1." Transactions of the Atomic Energy Society of Japan 14, no. 1 (2015): 12–24. http://dx.doi.org/10.3327/taesj.j14.003.

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16

Kovalchuk, M. V., B. B. Chaivanov, S. S. Abalin, and O. S. Feynberg. "Nuclear Power Unit with Molten Salt Fuel for the Arctic." Physics of Atomic Nuclei 82, no. 8 (December 2019): 1156–61. http://dx.doi.org/10.1134/s1063778819080088.

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17

Liu, Guangshi, Zhiyuan Sun, Qian Dou, Mosi Liu, Yihui Zhang, and Xiaoming Wang. "Analysis about modeling MEC7000 excitation system of nuclear power unit." IOP Conference Series: Earth and Environmental Science 121 (February 2018): 042030. http://dx.doi.org/10.1088/1755-1315/121/4/042030.

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18

Huterer, J., D. G. Brown, M. A. Osman, and E. C. Ha. "Pressure relief structures of multi-unit candu nuclear power plants." Nuclear Engineering and Design 100, no. 1 (February 1987): 21–39. http://dx.doi.org/10.1016/0029-5493(87)90069-0.

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19

Li, Wei, and Jian Feng Li. "Analysis on Control Operating Conditions of Water Chemistry of Nuclear Power Unit." Applied Mechanics and Materials 178-181 (May 2012): 553–56. http://dx.doi.org/10.4028/www.scientific.net/amm.178-181.553.

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Hydrochemical working condition of nuclear power plant relates to the safety, stability and economical operation of the whole plant. In view of radioactive factors, it is very important to analyze, identify and supervise the chemical control working condition. Based on AP1000 cases, this article analyzes issues through elaborating the primary system and the secondary system of nuclear power plant, especially the hydrochemical control of steam generator, and then takes targeted and effective control methods to provide references for the future nuclear power plants.

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20

Stanek, Wojciech, Jan Szargut, Zygmunt Kolenda, and Lucyna Czarnowska. "Influence of nuclear power unit on decreasing emissions of greenhouse gases." Archives of Thermodynamics 36, no. 1 (March 1, 2015): 55–65. http://dx.doi.org/10.1515/aoter-2015-0004.

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Abstract The paper presents a comparison of selected power technologies from the point of view of emissions of greenhouse gases. Such evaluation is most often based only on analysis of direct emissions from combustion. However, the direct analysis does not show full picture of the problem as significant emissions of GHG appear also in the process of mining and transportation of fuel. It is demonstrated in the paper that comparison of power technologies from the GHG point of view has to be done using the cumulative calculus covering the whole cycle of fuel mining, processing, transportation and end-use. From this point of view coal technologies are in comparable level as gas technologies while nuclear power units are characterised with lowest GHG emissions. Mentioned technologies are compared from the point of view of GHG emissions in full cycle. Specific GHG cumulative emission factors per unit of generated electricity are determined. These factors have been applied to simulation of the influence of introduction of nuclear power units on decrease of GHG emissions in domestic scale. Within the presented simulations the prognosis of domestic power sector development according to the Polish energy policy till 2030 has been taken into account. The profitability of introduction of nuclear power units from the point of view of decreasing GHG emissions has been proved.

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21

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

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

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22

Petrov, B. V., and A. S. Abakumov. "Atomic-power unit for long space flights." Atomic Energy 85, no. 6 (December 1998): 921–24. http://dx.doi.org/10.1007/bf02361127.

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23

Fang, Zhou. "Economic Factors Analysis and Optimization Strategy of Third-generation Nuclear Power." E3S Web of Conferences 292 (2021): 02024. http://dx.doi.org/10.1051/e3sconf/202129202024.

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Анотація:

Due to the project delay, the construction price of the first unit of the two types of third-generation nuclear motor type AP1000 and EPR in China is higher than the local benchmark price of coal. If the delay is not considered, only the first unit factor is considered, the price should be between 0.48-0.49 yuan/kWh. Compared with the construction period and electricity price of solar power generation and wind power, this price still has no advantage. Therefore, the economic efficiency of nuclear power has become a key factor to determine whether nuclear power can occupy a place in the future power market and then get rapid development. In this paper, combined with the construction experience of third-generation nuclear power in China, a comprehensive economic analysis of nuclear power is carried outfrom the design requirements, equipment procurement, construction period, financing channels, operation and maintenance strategies and other factors, so as to provide direction guidance for the economic improvement of the subsequent batch construction of the third-generation nuclear power and the better participation of nuclear power in the power market competition.

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24

Prasad, Mahendra, Gopika Vinod, Avinash J. Gaikwad, and A. Ramarao. "Site core damage frequency for multi-unit Nuclear Power Plants site." Progress in Nuclear Energy 96 (April 2017): 56–61. http://dx.doi.org/10.1016/j.pnucene.2016.12.007.

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25

Grobbelaar, J. F., N. A. S. Foster, and L. J. Lüsse. "Probabilistic fire risk assessment for Koeberg Nuclear Power Station Unit 1." International Journal of Pressure Vessels and Piping 61, no. 2-3 (January 1995): 571–78. http://dx.doi.org/10.1016/0308-0161(94)00128-6.

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26

Che, Yongqiang, Yisen Chen, Fengcai Zheng, Junshan Guo, and Panfeng Shang. "Operating characteristics and peak regulation capability of AP1000 nuclear power unit." IOP Conference Series: Earth and Environmental Science 714, no. 4 (March 1, 2021): 042033. http://dx.doi.org/10.1088/1755-1315/714/4/042033.

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27

Zhou, Taotao, Mohammad Modarres, and Enrique López Droguett. "Multi-unit nuclear power plant probabilistic risk assessment: A comprehensive survey." Reliability Engineering & System Safety 213 (September 2021): 107782. http://dx.doi.org/10.1016/j.ress.2021.107782.

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28

Guo, Zhong De, and Shu Fang Zhang. "The Pure Heat Conversion Coefficient Analysis Method for Thermodynamic System of Advance Boiling Water Reactor Nuclear Power Unit." Advanced Materials Research 383-390 (November 2011): 6514–18. http://dx.doi.org/10.4028/www.scientific.net/amr.383-390.6514.

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Анотація:

Pure heat conversion coefficient, which is one important parameter for the advance boiling water reactor nuclear power unit, is defined, and the coefficient reflects energy grade values of heaters. According to the structural characteristics of the thermodynamic system of the advanced boiling water reactor nuclear power plant, four sorts of auxiliary steam-water components are categorized. Via strict deduction and demonstration, the general matrix of the coefficient is deduced, so the thermal economic analysis of advance boiling water reactor nuclear power unit can be done with one of extraction steam efficiency. In this way, a new method of thermal economic quantitative analysis for this unit is offered.

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29

Yurin, Valery, and Dmitry Bashlykov. "Predictive and comparative analysis of NPP modernization with an autonomous hydrogen power complex and gas turbine unit." Energy Safety and Energy Economy 3 (June 2021): 22–30. http://dx.doi.org/10.18635/2071-2219-2021-3-23-30.

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Optimizing existing nuclear power plants adding developing power technology can help find effective ways of improving variable power loads in an electric power system. One of the most promising options is combining a nuclear power plant with a newly developed autonomous hydrogen complex reported in our research. The ability of storing unused energy and releasing it when needed will raise contribution of nuclear power plants in compensating improving variable power loads, shorten emissions as well as contribution of conventional thermal power plants into electric power generation. Also, as we demonstrated in our previous research results, a low-power steam turbine plant used in the said autonomous hydrogen complex can support an auxiliary power system of a nuclear power plant reusing residual reactor heat in case of an outage.

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30

Wang, Xiao Hui, Li Zi Zhang, Zhuo Xin Sun, and Shi Jun Cheng. "Evaluate Pumped-Storage Unit in Power System with Multi-Type Units." Applied Mechanics and Materials 392 (September 2013): 586–92. http://dx.doi.org/10.4028/www.scientific.net/amm.392.586.

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This paper proposed an approach to evaluate the economics of pumped-storage unit from the perspective of the power system. An MIP-based unit commitment model with multi-type units was established, which integrated thermal, CCGT, hydro, wind, nuclear and pumped-storage units. Based on the model the net present value of pumped-storage per megawatt was calculated and compared with the capital cost per megawatt, which produce the economic result of pumped-storage. The case study proved the feasibility of the above model and approach. Furthermore, the change of economic result of pumped-storage over system variables like nuclear capacity, wind capacity and regulating capacity of thermal unit was analyzed. The case study showed that with the increase of nuclear capacity, wind capacity and minimum output of thermal units, the economics of pumped-storage was improved.

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31

Gabielkov, S. V., I. V. Zhyganiuk, V. G. Kudlai, P. E. Parkhomchuk, and S. A. Chikolovets. "Phase composition of non-irradiated nuclear fuel from 4th unit of Chornobyl Nuclear Power Plant." Nuclear Power and the Environment 14, no. 2 (2019): 21–25. http://dx.doi.org/10.31717/2311-8253.19.2.3.

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32

Chen, Hai Qiao, Yi Mu Qiu, Xiao Wei Wang, and Ying Yu. "Discussion and Application of Passive Hydrogen Recombiner in Qinshan Phase II Nuclear Power Plant." Advanced Materials Research 1008-1009 (August 2014): 215–20. http://dx.doi.org/10.4028/www.scientific.net/amr.1008-1009.215.

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A large amount of hydrogen would be generated because of zirconium-water reaction during serious accidents in nuclear power plant (NPP). Hydrogen could be combusted or explode under certain conditions, resulting in damage of the containment integrity and releasing radioactive substances into surrounding environment. Therefore, hydrogen elimination inside the NPP containment is an important subject. According to the requirements of NNSA (National Nuclear Security Administration), enough passive hydrogen recombiners (PHR) had been installed in unit 3&4 of Qinshan phase II NPP to prevent the hydrogen explosion in a serious accident. Additionally, new PHRs for unit 1&2 were also added. This article introduces the practical experience for the PHR modification, the comparisons between unit 1&2 and unit 3&4.

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33

Gusev, Igor Nikolaevich, Vladimir Ruslanovich Kazanskiy, and Igor Leonidovich Vitkovsky,. "Dynamic stability of the VVER-1200 power unit." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2017, no. 3 (October 2017): 22–32. http://dx.doi.org/10.26583/npe.2017.3.02.

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34

Baek, Sejin, and Gyunyoung Heo. "Application of Dynamic Fault Tree Analysis to Prioritize Electric Power Systems in Nuclear Power Plants." Energies 14, no. 14 (July 8, 2021): 4119. http://dx.doi.org/10.3390/en14144119.

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Анотація:

Because the scope of risk assessments at nuclear power plants (NPPs) is being extended both spatially and temporally, conventional, or static fault trees might not be able to express failure mechanisms, or they could be unnecessarily conservative in their expression. Therefore, realistic assessment techniques are needed to adequately capture accident scenarios. In multi-unit probabilistic safety assessment (PSA), fault trees naturally become more complex as the number of units increases. In particular, when considering a shared facility between units of the electric power system (EPS), static fault trees (SFTs) that prioritize a specific unit are limited in implementing interactions between units. However, dynamic fault trees (DFTs) can be available without this limitation by using dynamic gates. Therefore, this study implements SFTs and DFTs for an EPS of two virtual NPPs and compares their results. In addition, to demonstrate the dynamic characteristics of the shared facilities, a station blackout (SBO), which causes the power system to lose its function, is assumed—especially with an inter-unit shared facility, AAC DG (Alternate AC Diesel Generator). To properly model the dynamic characteristics of the shared EPS in DFTs, a modified dynamic gate and algorithm are introduced, and a Monte Carlo simulation is adopted to quantify the DFT models. Through the analysis of the DFT, it is possible to confirm the actual connection priority of AAC DG according to the situation of units in a site. In addition, it is confirmed that some conservative results presented by the SFT can be evaluated from a more realistic perspective by reflecting this.

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35

Chesnokova, I., S. Verbitsky, and E. Stambrovskaya. "Analysis of the possibility for operating a floating nuclear power plant in conjunction with a desalination plantAnalysis of the possibility for operating a floating nuclear power plant in conjunction with a desalination plant." Transactions of the Krylov State Research Centre 2, no. 396 (May 21, 2021): 149–58. http://dx.doi.org/10.24937/2542-2324-2021-2-396-149-158.

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Анотація:

Object and purpose of research. The article discusses in comparison the methods of desalination of seawater and their energy features from the point of view of the feasibility of including a desalination plant in the complex with a floating nuclear power unit. Materials and methods. Based on the analysis of various literary sources, a review of the main methods of nuclear desalination is made. The IAEA DEEP program was used to compare different desalination technologies. Main results. Based on the results of simulating nuclear desalination in the IAEA DEEP program, using the example of the Persian Gulf, preliminary recommendations were drawn up on the use of desalination methods in the joint operation of a desalination plant with a floating nuclear power unit. Conclusion. The integrated complex allows for desalination by both membrane and thermal methods. For the optimal choice of technology, it is necessary to specify the area of deployment and the relative position of the floating nuclear power unit and the desalination plant, and further search for a compromise based on more accurate calculations.

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36

Wang, Dean, Ian C. Gauld, Graydon L. Yoder, Larry J. Ott, George F. Flanagan, Matthew W. Francis, Emilian L. Popov, et al. "Study of Fukushima Daiichi Nuclear Power Station Unit 4 Spent-Fuel Pool." Nuclear Technology 180, no. 2 (November 2012): 205–15. http://dx.doi.org/10.13182/nt12-a14634.

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37

Yang, Joon-Eon. "Multi-unit risk assessment of nuclear power plants: Current status and issues." Nuclear Engineering and Technology 50, no. 8 (December 2018): 1199–209. http://dx.doi.org/10.1016/j.net.2018.09.010.

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38

Yamashita, Takuya, Ikken Sato, Takeshi Honda, Kenichiro Nozaki, Hiroyuki Suzuki, Marco Pellegrini, Takeshi Sakai, and Shinya Mizokami. "Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2." Nuclear Technology 206, no. 10 (March 2, 2020): 1517–37. http://dx.doi.org/10.1080/00295450.2019.1704581.

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39

Wang, Chenglong, Jing Chen, Suizheng Qiu, Wenxi Tian, Dalin Zhang, and G. H. Su. "Performance analysis of heat pipe radiator unit for space nuclear power reactor." Annals of Nuclear Energy 103 (May 2017): 74–84. http://dx.doi.org/10.1016/j.anucene.2017.01.015.

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40

Sheta, Amal A., Elsayed H. Ali, Refaat M. Fikry, Sayed M. ElAraby, Tarek A. Mahmoud, and Mohammed I. Mahmoud. "A developed analytical model for the pressurizer unit in nuclear power plants." Journal of Radiation Research and Applied Sciences 14, no. 1 (January 1, 2021): 179–203. http://dx.doi.org/10.1080/16878507.2021.1885950.

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41

Jung, Woo Sik, Joon-Eon Yang, and Jaejoo Ha. "A new method to evaluate alternate AC power source effects in multi-unit nuclear power plants." Reliability Engineering & System Safety 82, no. 2 (November 2003): 165–72. http://dx.doi.org/10.1016/s0951-8320(03)00140-6.

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42

Yang, Zuo Liang, Zhi Gang Dai, and Tong Bin Wang. "Feed-Water Enthalpy Rise Optimum Distribution Mechanism Model of PWR Nuclear Power Unit Based on Genetic Algorithm." Advanced Materials Research 1008-1009 (August 2014): 231–36. http://dx.doi.org/10.4028/www.scientific.net/amr.1008-1009.231.

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Анотація:

This paper presented a novel method for using Genetic Algorithm (GA) to solve the problem of Feed-water Enthalpy Rise Optimum Distribution in nuclear power unit. According to the characteristics of the pressurized-water reactor unit's secondary circuit, the calculation equations for the power and the heat rate of steam turbine are given in matrix form, the rate of extraction steam is calculated by the general matrix thermal balance equation, and then receive the equation of the efficiency of steam turbine which has relative with parameters of every node in the thermodynamic system in PWR unit. Taking the efficiency equation as aim function, an effective fitness-model was established with the appropriate optimum parameters under the restriction condition, the feed-water enthalpy rise distribution is optimized under the restriction condition by means of Genetic Algorithm. Through the calculation of a 600MW PWR nuclear power unit, the results indicate that Genetic Algorithm has global searching performance, gives a better global optimum than original design value rapidly and shows the relations between the optimum parameters (even the temp parameters) and the optimization easily. Genetic Algorithm is a promising method for analyzed and solved the feed-water enthalpy rise optimum distribution in PWR nuclear power unit.

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43

Dyachenko, Petr P., Anatoly V. Zrodnikov, Oleg F. Kukharchuk, and Alexey A. Suvorov. "Problem of nuclear-laser power engineering and methods of their solution." Nuclear Energy and Technology 5, no. 3 (September 25, 2019): 257–63. http://dx.doi.org/10.3897/nucet.5.46381.

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The concept of a high power reactor-laser system based on a nuclear pumped optical quantum amplifier (OKUYaN) was formulated at IPPE in the mid-1980-ies. The idea amounted to the use of wide-aperture OKUYaN as an amplifier within the already well-known “master laser – two-pass amplifier with phase conjugation” scheme. The structure of such an amplifier includes a system of two neutron-coupled units – an ignition reactor (RB) and a nuclear pumped laser amplifier (LB). The ignition unit is a compact multi-core pulsed fast neutron reactor. The laser amplifier unit operates on thermal neutrons and, with regard to the neutronics, it is a subcritical booster zone of the ignition reactor unit. Unique reactor-laser complex incorporating demonstration sample of a pulsed reactor-laser system based on OKUYaN (test facility “Stand B”) having no analogues anywhere in the world, was developed and put into operation at IPPE in 1999 for the purpose of substantiation of basic principles of the OKUYaN concept and demonstration of the possibility of its practical implementation, as well as verification of calculation codes and development of relevant equipment elements. Problems overcome in the development and construction of “Stand B” test facility, the choice and justification of the neutronics and laser characteristics of the OKUYaN demonstration sample are discussed in the present paper. Provided are the results of a detailed computational-experimental study of the demonstration sample characteristics, the data from systems studies of direct conversion of nuclear fission energy into laser radiation energy in complex reactor-laser devices and the results of examination of prospects for the development of nuclear-laser power engineering.

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44

Danilov, Alexander, Vladimir Povarov, Viktor Burkovsky, Semen Podvalny, and Konstantin Gusev. "Intellectual decision-making system in the context of potentially dangerous nuclear power facilities." MATEC Web of Conferences 161 (2018): 02009. http://dx.doi.org/10.1051/matecconf/201816102009.

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Анотація:

The article deals with intelligent operation decision support system under condition of potentially hazardous nuclear facilities. The proposed system is referred to the class of advising systems and does not make final decisions in case of deviations of parameters to be analyzed, but generates general ways to solve an encountered problem and issues a set of recommendations for the plant personnel. In the article a fuzzy logic tool is used as mathematic tool. Lessons learnt from operation of nuclear facilities demonstrate that existing critical components (parts, areas, welding joints) are subject to increased failure under conditions of high operational loads, including beyond design loads and negative environmental impact. Usually in that situation there is probability of equipment integrity failure, when the unit is at power, with severe defect downing. For instance, the coolant leak and potential development of initial penetration defect to critical dimensions. In other words, in fact, the final observable result is always one – formation and development of operational crack which jeopardizes design integrity of the component and, accordingly, seriously compromises the nuclear power unit operation. The proposed situational model is linked with real knowledge data base where generated situational pairs are stored. The expert system is used for knowledge data base formation. Actually the proposed system consists of two independent fuzzy systems. From mathematical tool point of view, the advantage of such systems combination is lack of defuzzification unit in the first system and fuzzification unit in the second one.

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45

Dong, Li Yu, Zhi Wei Zhou, and Yang Ping Zhou. "Mathematical Model and Dynamic Characteristics of Spiral-Style Super-Critical Steam Generator Used HTGR." Advanced Materials Research 347-353 (October 2011): 1678–82. http://dx.doi.org/10.4028/www.scientific.net/amr.347-353.1678.

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Анотація:

Modular HTGR nuclear power plant because of inherent safety and high thermal efficiency shows good prospects for development. The current high-temperature reactor demonstration power plant (HTR-PM) using two thermal power of 250MW of modular HTGR with an electric power 211MWe turbine unit. As one development goals of multi-reactor with one turbine unit, millions of kilowatt nuclear power plant will use more reactor module and steam generator module more like demonstration power plant (HTR-PM) with 1000MWe supercritical turbine generator unit. spiral-style super-critical steam generator design, modeling is a key factor. Analyzing the structure and the characteristic of moderate spiral coil steam generator which is used in Modular HTGR demonstration power plant, from the mechanism of equipments, based on the law of quality conservation, energy conservation, momentum conservation, authors build up the full scope real time simulation mathematical model of super critical steam generator. The dynamic experiments of feed water disturbance, power disturbance, Helium flux disturbance are made on the basis of the model. The experiments show that the model of super critical steam generator has excellent dynamic characteristics.

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46

Grigoreva, Larisa, and Vladimir Grigoryev. "Development of an intelligent system of experimental control in the energy sector." E3S Web of Conferences 164 (2020): 13003. http://dx.doi.org/10.1051/e3sconf/202016413003.

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Анотація:

The article presents a completed project of an experimental control system in the energy sector. An intelligent experimental control system can be used at various types of power plants, including nuclear power units. The developed complex includes design schemes for operational monitoring and registration of rapidly changing neutron-physical and technological parameters of a nuclear power unit at the stages of commissioning of a power unit. Automated process control systems allow the collection and registration of analog parameters with a frequency of not more than 1 second, which is insufficient for correct calculations during neutron-physical experiments and power unit tests. The presented intelligent experimental control system allows the reception and registration of analog signals with a frequency of not more than 100 millisecond. A patented software implementation has been developed that provides unlimited possibilities for realizing customer requirements for operator functionality and interface, as well as the ability to avoid tight binding to specific hardware components.

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47

Podlazov, L. N., V. E. Trekhov, Yu M. Cherkashov, P. Loizzo, A. Galati, and F. Norelli. "Computational modeling of the accident in the fourth power-generating unit of the chernobyl nuclear power plant." Atomic Energy 77, no. 2 (August 1994): 580–87. http://dx.doi.org/10.1007/bf02407430.

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48

Baran, P., Y. Varetsky, V. Kidyba, and Y. Pryshliak. "A mathematical model for the virtual simulator of the power unit electrical part." IOP Conference Series: Materials Science and Engineering 1216, no. 1 (January 1, 2022): 012009. http://dx.doi.org/10.1088/1757-899x/1216/1/012009.

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Анотація:

Abstract The mathematical model is developed for a virtual training system (simulator) of the power unit electrical part operators of a thermal (nuclear) power plant. The model is used to simulating the main operating conditions of the power unit electrical part: generator idling, generator synchronization with the power system, excitation shifting from the main unit to the backup one and vice versa, switching in the power unit auxiliary system, and others. Furthermore, it has been implemented modelling some probable emergency conditions within a power plant: incomplete phase switching, damage to standard power unit equipment, synchronous oscillations, asynchronous mode, etc. The model of the power unit electrical part consists of two interacting software units: models of power equipment (turbine, generator with excitation systems, auxiliary system) and models of its control systems, automation, relay protection and signalling. The models are represented by the corresponding algebraic-differential equations that provide real-time mapping power unit processes at the operator’s request. The developed model uses optimal solving algebraic-differential equations to ensure the virtual process behaviour in real-time. In particular, the implicit Euler method is used to solve differential equations, which is stable when simulating processes in significant disturbances, such as accidental disconnection of the unit from the power system, tripping and energizing loads, generator excitation loss, etc.

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49

Vo, Truong V., Frederic A. Simonen, Steven R. Doctor, Brian W. Smith, and Bryan F. Gore. "Development of In-Service Inspection Plans for Nuclear Components at the Surry Unit 1 Nuclear Power Station." Nuclear Technology 102, no. 3 (June 1993): 403–15. http://dx.doi.org/10.13182/nt93-a17038.

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50

Sohrabi, M., M. Ghasemi, R. Amrollahi, C. Khamooshi, and Z. Parsouzi. "Assessment of environmental public exposure from a hypothetical nuclear accident for Unit-1 Bushehr nuclear power plant." Radiation and Environmental Biophysics 52, no. 2 (January 29, 2013): 235–44. http://dx.doi.org/10.1007/s00411-013-0456-y.

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