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Journal articles on the topic 'Unit of nuclear power plant'

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Published: 30 May 2022
Last updated: 31 May 2022

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1

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

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2

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

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

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

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4

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

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

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

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

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7

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

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8

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

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9

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

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

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

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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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11

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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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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12

Fu, Wen Feng, Fe Li, and Lan Xin Zhou. "Application of PSO in the Optimization of Nuclear Power Unit’s Heat Regenerative System." Advanced Materials Research 986-987 (July 2014): 698–701. http://dx.doi.org/10.4028/www.scientific.net/amr.986-987.698.

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Based on theoretical deduction, according to the characteristics of nuclear power unit, a universal heat economic framework for PWR nuclear power plant heat regenerative system was established. And on this basis, the cycle thermal efficiency was chosen as the optimization goal, the extraction steam pressures were chosen as optimization variables, a universal nuclear power unit regenerative system optimization model was established. A 900 MW nuclear power unit was taken for example, it’s the first time that AWPSO was applied to optimize the regenerative heat system of nuclear power unit. The result shows that the convergence ability and search performance of PSO are superior to other methods and the original design scheme. A new and convenient design is provided for PWR nuclear power plant heat regenerative system in this paper.
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13

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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14

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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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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15

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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16

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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17

Zevin, Leonid I., and Hennadii H. Krol. "Optimization of Systems Repair Plans and Assessment of the Useful Life of Nuclear Power Plant Equipment." Journal of Mechanical Engineering 23, no. 4 (December 30, 2020): 72–78. http://dx.doi.org/10.15407/pmach2020.04.072.

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This paper presents a computer-aided method of planning the volumes of repairs of systems of nuclear power units and a method for calculating their gamma-percentile life. This planning is carried out on the basis of predicting the reliability indicator, the probability of no-failure operation for a certain time period, with the gamma-percentile life of the equipment being determined by solving the corresponding equations. The tasks considered are related to an important energy problem of extending the operation of nuclear power units. Its importance is determined mainly by economic feasibility: it is cheaper to assess the useful life of a nuclear power unit and, on this research basis, extend its operation, than create a new unit. It is also shown that the calculation of the probability of a radiation accident at a nuclear power unit is associated with the results of planning the repairs of its systems, with assessment of its useful life. An optimization problem is formulated: it is required to find such a plan for the volumes of repair of a system that, with limited repair costs, its reliability indicator for a given duration deviates least from the maximum permissible value. The solution to the problem is based on calculating the structural reliability of the system. A graphological image of the system is built in the form of a composition of graphological images of typical structures. After the reliability indicator of typical structures has been calculated, the structures are replaced with individual structural elements, which makes it possible to simplify the initial graphological image of the system in a computational scenario and calculate its reliability indicator. The determination of the repair volume is carried out by applying a version of the coordinate-wise optimization method. To assess the gamma-percentile life, a model is adopted, in which the recoverable equipment components have an unlimited life, although, of course, they "age", and the non-recoverable components spend their life up to the level when their replacement becomes conditioned by the violation of the requirement for the maximum permissible value of the system reliability indicator. Estimates of the gamma-percentile life of the equipment are calculated by planning system repairs on a sequence of intervals of annual energy production by a nuclear power unit.
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18

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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19

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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20

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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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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21

Alejev, Aleksandr, Mečislovas Griškevičius, Ritoldas Šukys, Ian Frith, and Antti Norta. "REVIEW OF FIRE HAZARD ANALYSIS OF IGNALINA NUCLEAR POWER PLANT." JOURNAL OF CIVIL ENGINEERING AND MANAGEMENT 10, no. 3 (September 30, 2004): 169–75. http://dx.doi.org/10.3846/13923730.2004.9636303.

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Fire safety is important throughout the lifetime of a plant, from design to construction and commissioning, throughout plant operation and to decommissioning. The article is the document that will present the review results of the documents by VATESI during licensing Unit 1, 2 and provides information how Ignalina NPP to meet State requirements and international recommendations to achieve and maintain satisfactory fire safety. Fire hazard analysis of operation RBMK‐1500 type reactor is done for first time in the world practice.
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22

Çolak, E., M. Chandra, and F. Sunar. "THE USE OF MULTI-TEMPORAL SENTINEL SATELLITES IN THE ANALYSIS OF LAND COVER/LAND USE CHANGES CAUSED BY THE NUCLEAR POWER PLANT CONSTRUCTION." ISPRS - International Archives of the Photogrammetry, Remote Sensing and Spatial Information Sciences XLII-3/W8 (August 23, 2019): 491–95. http://dx.doi.org/10.5194/isprs-archives-xlii-3-w8-491-2019.

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<p><strong>Abstract.</strong> Turkey, due to increased demand for energy has made plans for nuclear power generation since 1970. Sinop Nuclear Power Plant, which will be built on Sinop İnceburun peninsula at the Black Sea coast of Turkey, is one of the three different nuclear power plants planned to be built in Turkey. The Sinop Nuclear Power Plant consist of four different reactors. The construction of the first unit is expected to be completed by 2023, and the fourth unit is planned to be activated by 2028. On the other hand, the construction of the nuclear power plant will alter the land use at the actual plant site and its surroundings and hence may cause significant environmental changes. As an indicator, more than 650000 trees have been cut so far for the construction of nuclear power plant, and this can adversely affect the ecological balances of the region by endangering habitats and creating ecological damages. The aim of this study is to analyse the land use/land cover changes (LULC) in the forestry-dominated areas due to the construction of nuclear power plants using the multi-temporal Synthetic Aperture Radar (SAR) and optical satellite images. For this purpose, different change detection methods such as SAR intensity image differencing, supervised image classification method (Support Vector Machine algorithm) were applied to Sentinel 1 satellite image datasets (2016-2019) to evaluate the annual changes due to construction. In addition, a correlation analysis was performed between the canopy structure and vegetation biomass using Sentinel 2 NDVI dataset (2016-2019) and calibrated Sentinel 1 backscatter values. Furthermore, using the Google Earth Engine (GEE), the Landsat 8 NDVI time series of the affected forest area, generated at 8-day intervals, was used to validate changes in vegetation.</p>
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23

Babushkin, Aleksey, Sergey Skubienko, and Ludmila Kinash. "Study of the Rostov nuclear power plant efficiency operation under increased vacuum value." MATEC Web of Conferences 329 (2020): 03049. http://dx.doi.org/10.1051/matecconf/202032903049.

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In this study, the influence of the cooling water temperature on the thermal efficiency of a conceptual pressurized-water reactor nuclear- power plant is studied. The change in the cooling water temperature can be experienced due to the seasonal changes in climatic conditions at plant site. The article presents the results of technical and economic parameters study of nuclear power unit’s operation under increased vacuum value. Investigated seasonal variations of cooling water temperature, cooling water temperature influence on the vacuum temperature in the turbine condenser, and changing the basic technical and economic performance of nuclear power station. The mathematical model of calculation the nuclear power plant operation for a 1000 MW power unit was developed.
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24

Ansorge, Libor, and Jiří Dlabal. "Comparative water scarcity footprint study of two nuclear power plants." Przegląd Naukowy Inżynieria i Kształtowanie Środowiska 26, no. 4 (December 30, 2017): 489–97. http://dx.doi.org/10.22630/pniks.2017.26.4.47.

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This study compares the Life Cycle Assessment based Water Scarcity Footprint of produced energy unit in two nuclear power plants in the Czech Republic between 2005 and 2015. Primary data has been used to allocate impacts to the core processing stage. Although the real total amount of water consumption in both power plants is similar, the water scarcity footprint in Temelín nuclear power plant is of approximately 8.9 m3 H2Oeq per MWh lower than in Dukovany power plant. The cooling water has the most significant contribution to the freshwater availability impact category. Evaporation from reservoirs which are a part of water management of the individual power plants has lower, but not inconsiderable, contribution to the water consumption. In the case of Temelín nuclear power plant, the loss caused by evaporation from Hněvkovice reservoir is of approximately 6.5% of the difference between withdrawal and discharge of the power plant. In the case of Dukovany nuclear power plant, evaporation from Dalešice - Mohelno reservoir is of even around 11%.
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Koltun, Paul, Alfred Tsykalo, and Vasily Novozhilov. "Life Cycle Assessment of the New Generation GT-MHR Nuclear Power Plant." Energies 11, no. 12 (December 10, 2018): 3452. http://dx.doi.org/10.3390/en11123452.

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This study describes a life cycle assessment (LCA) of a fourth generation (4G) nuclear power plant. A high temperature helium cooled reactor and gas turbine technology with modular helium reactor (GT-MHR) is used in this study as an example. This is currently one the safest design of a nuclear power plant. The study also takes into account impact of accidents and incidents (AI) which happened around the world at nuclear power generation facilities. The adopted method for the study is a hybrid LCA analysis. The analysis of each phase of the life cycle was done on the basis of process chain analysis (PCA). Where detailed data were not available, the Input/Output (I/O) databases was employed. The obtained results show that greenhouse gases (GHG) emissions and energy intensity per unit of electricity production are relatively low. In fact, these are even lower than emissions from a number of renewable energy sources. The results show considerably different greenhouse gases (GHG) emissions and energy intensity per unit of electricity production when effects of AI are taken into account.
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26

Liu, Ao, Pengcheng Peng, Tao Liu, and Jiejuan Tong. "A plant operating state analysis method in probabilistic safety assessment for multi-unit nuclear power plant." Annals of Nuclear Energy 169 (May 2022): 108952. http://dx.doi.org/10.1016/j.anucene.2021.108952.

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27

Zorin, Vyacheslav M., Irina V. Ustyukhina, and Anastasiya V. Besova. "The Energy Balance and Thermal Efficiency Indicators of a Nuclear Power Plant Unit." Vestnik MEI 2, no. 2 (2020): 34–41. http://dx.doi.org/10.24160/1993-6982-2020-2-34-41.

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28

Zhang, Sai, Mengyu Du, Jiejuan Tong, and Yan-Fu Li. "Multi-objective optimization of maintenance program in multi-unit nuclear power plant sites." Reliability Engineering & System Safety 188 (August 2019): 532–48. http://dx.doi.org/10.1016/j.ress.2019.03.034.

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29

Raskin, E. M., L. A. Denisova, V. P. Sinitsyn, and Yu V. Nesterov. "Mathematical model of steam generator feed system at power unit of nuclear plant." Automation and Remote Control 72, no. 5 (May 2011): 1118–26. http://dx.doi.org/10.1134/s0005117911050213.

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Lee, Jong-Bin, and Seong Rok Chang. "Assessment of risk of unit work in nuclear power plant construction using AHP." Journal of the Korean Society of Safety 29, no. 2 (April 30, 2014): 62–67. http://dx.doi.org/10.14346/jkosos.2014.29.2.062.

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31

Varpasuo, P., J. Puttonen, and M. K. Ravindra. "Seismic probabilistic safety analysis of unit 1 of the Loviisa nuclear power plant." Nuclear Engineering and Design 160, no. 3 (February 1996): 411–26. http://dx.doi.org/10.1016/0029-5493(95)01118-8.

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32

Hassija, Varun, C. Senthil Kumar, and K. Velusamy. "Probabilistic safety assessment of multi-unit nuclear power plant sites – An integrated approach." Journal of Loss Prevention in the Process Industries 32 (November 2014): 52–62. http://dx.doi.org/10.1016/j.jlp.2014.07.013.

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33

Zhang, Tao, Xiao Dong Ma, Yu Zhu, Gang Wang, and Peng Ye. "A Research Summary on Combined Peaking Load Strategies of Nuclear Power Plant." Advanced Materials Research 986-987 (July 2014): 196–201. http://dx.doi.org/10.4028/www.scientific.net/amr.986-987.196.

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Based on extensive research, introduced the peak load regulation characteristics and capacity of different nuclear power plant (NPP) in this paper. The running mode of NPP participating in peak load regulation of power system, combined operation tactics of NPP with other peaking power source and synergistic scheduling of an integrated power generation system with wind, photovoltaic, energy storage unit and NPP were summarized, technology development trend of NPP participating in peak load regulation of power system was analyzed and forecasted.
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34

Rivenbark, E. R., and G. W. Mouland. "New Thermal Generating Plant Projects in New Brunswick." Energy Exploration & Exploitation 13, no. 4 (August 1995): 385–92. http://dx.doi.org/10.1177/014459879501300409.

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New Brunswick Power Corporation's electrical generating system is well diversified with electrical power produced by a mix of hydro, fossil and nuclear generating plants. Recently, in developing aditional generating capacity, keeping a diversity of fuel options was key in New Brunswick Power Corporation's plans. The recently completed 450 megawatt (net) Belledune Generating Station which is currently fired on coal, includes boiler design provisions so that it could be converted to operate on bunker “C” or Orimulsion™ (Note 1). The conversion of the 100 MW bunker “C” unit and the 212 MW coal fired unit at Dalhousie to Orimulsionxx firing provides access to a significant new fuel on the world market.
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35

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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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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Bustamante, Ricardo, Gilberto Mosqueda, and Minkyu Kim. "Enhanced Seismic Protection System for an Emergency Diesel Generator Unit." Energies 15, no. 5 (February 25, 2022): 1728. http://dx.doi.org/10.3390/en15051728.

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Nuclear power plants are required to maintain operation after an earthquake, leading to a safe shutdown if necessary. In the case of a loss of offsite power, the onsite emergency diesel generator is critical to ensure procedural operations of the nuclear power plant. As a means to reduce the overall seismic risk, a three-dimensional seismic protection system is proposed to enhance the seismic performance of the emergency diesel generator. The proposed seismic isolation system decouples the horizontal and vertical components of shaking and considers available hardware to achieve an effective isolation solution over the range of excitation frequencies considered. Numerical analysis of the proposed system demonstrates a reduction in seismic demands on the emergency diesel generator and provides a higher safety margin than conventional base installation procedures. Umbilical lines that cross the isolation plane are considered and impose additional constraints on the displacement capacity of the isolation system. However, increasing the displacement capacity of these components can significantly increase the safety margin against failure. The seismic protection system can be customized depending on the seismic hazard and application to different seismic regions.
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37

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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38

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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39

HANNA, BOTROS N., LY LY T. TRIEU, TRAN C. SON, and NAM T. DINH. "An Application of ASP in Nuclear Engineering: Explaining the Three Mile Island Nuclear Accident Scenario." Theory and Practice of Logic Programming 20, no. 6 (September 22, 2020): 926–41. http://dx.doi.org/10.1017/s1471068420000241.

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AbstractThe paper describes an ongoing effort in developing a declarative system for supporting operators in the Nuclear Power Plant (NPP) control room. The focus is on two modules: diagnosis and explanation of events that happened in NPPs. We describe an Answer Set Programming (ASP) representation of an NPP, which consists of declarations of state variables, components, their connections, and rules encoding the plant behavior. We then show how the ASP program can be used to explain the series of events that occurred in the Three Mile Island, Unit 2 (TMI-2) NPP accident, the most severe accident in the USA nuclear power plant operating history. We also describe an explanation module aimed at addressing answers to questions such as “why an event occurs?” or “what should be done?” given the collected data.
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40

王, 兵. "Introduction to Emergency Response Organization for Multi-Unit Events in Ningde Nuclear Power Plant." Nuclear Science and Technology 02, no. 03 (2014): 45–51. http://dx.doi.org/10.12677/nst.2014.23008.

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41

Oshkanov, N. N., M. V. Bakanov, and O. A. Potapov. "Experience in Operating the BN-600 Unit at the Belyi Yar Nuclear Power Plant." Atomic Energy 96, no. 5 (May 2004): 315–19. http://dx.doi.org/10.1023/b:aten.0000038096.18551.aa.

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42

Terekhov, D. V., and V. I. Dunaev. "Upgrading the fuel-handling machine of the Novovoronezh nuclear power plant unit no. 5." Thermal Engineering 61, no. 2 (January 5, 2014): 139–43. http://dx.doi.org/10.1134/s0040601514020128.

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43

Kiselev, A. N., A. I. Surin, and K. P. Checherov. "Post-accident survey of the unit 4 reactor of the Chernobyl nuclear power plant." Atomic Energy 80, no. 4 (April 1996): 225–31. http://dx.doi.org/10.1007/bf02419299.

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44

Harishwar, D., S. N. Amresh, S. Prabhakar, V. Murugan, and M. Magesh Kumar. "Performance analysis of operating multi-stage flash distillation unit coupled with nuclear power plant." DESALINATION AND WATER TREATMENT 251 (2022): 134–45. http://dx.doi.org/10.5004/dwt.2022.28295.

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45

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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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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46

Hu, Yanjun, Tian Wan, Weiwei Pan, Shengzhi Liu, and Min Li. "The Design of Thermodynamic System Instrument & Control for the Daya Bay Turbine High Pressure Cylinder Retrofit." Journal of Physics: Conference Series 2247, no. 1 (April 1, 2022): 012028. http://dx.doi.org/10.1088/1742-6596/2247/1/012028.

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Abstract Before the retrofit, the equipments of the turbine high pressure cylinder of the Daya Bay Nuclear Power Plant is of the old technology. The design of the leaf shape and the steam runner is not advanced, and the equipments are aged after more than 20 years’ operation. From the point of increasing the power and improving the reliability of the equipments, it’s decided to retrofit the turbine high pressure cylinder of Daya Bay Nuclear Power Plant unit 1 and unit 2. The retrofit relates to the design and modification of many secondary loop thermodynamic systems’ instrument & control parameters, in order to match with the first loop reactor control systems, and also the mechanism and electric systems, it’s necessary to verify and optimize these designed parameters of the units after the retrofit. This design and analysis method and experience of the secondary loop thermodynamic systems’ instrument & control parameters can be referred by the similar retrofit of other nuclear power plants.
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47

Zhmaylov, Vadim V., Andrew Iu Kozhenikov, and Olga A. Korovina. "The application of the nuclear power plant measuring channels complete verification." Izmeritel`naya Tekhnika, no. 5 (2020): 4–10. http://dx.doi.org/10.32446/0368-1025it.2020-5-4-10.

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It’s suggested to develop the additional NPP measuring channels verification regulations in order to reduce verification labour-intensiveness and increase economic NPP operation efficiency. This regulations should afford an opportunity for componentwise verification and for basic and alternative complete verification of the NPP measuring channels depending on the verification reliability requirements. The uniformly precise, cross and combined methods are identified as alternative methods of complete verification. This article proposes the main regulations development problems and presents requirements for the basic regulations provisions. It’s emphasized that the developed regulations of the provisions on the application complete verification of the NPP measuring channels should allow: to control the channel error as a single measuring device without demounting its components; to reduce the verification time allocated during power generating unit hold; to preserve the acceptable level of the measurement channel verification results reliability. An example of the complete verification reliability estimation procedure is given as one of the most important criteria for selecting the verification method.
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48

Sobolev, Artem V., Igor A. Tutnov, and Vladimir F. Ukraintsev. "Assessment of the personnel reliability indicators during long-term operation of a nuclear power plant unit." Nuclear Energy and Technology 6, no. 2 (June 19, 2020): 83–88. http://dx.doi.org/10.3897/nucet.6.54622.

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The purpose of the work is to form and discuss the key components of the methodology to obtain the quantitative indicators of the personnel reliability based on the actual long-term operation experience data for a particular power unit. The timeliness of this work and similar studies is based on a simple judgment that the personnel reliability performance at similar units, in the best case, and in associated industries, in the worst case, that is, the reliability of personnel at other industrial facilities, is used to justify the design when designing power plant units. Accordingly, the obtained safety assessments with respect to personnel have nothing to do with the facility the safety of which is justified. This requires respective methods and procedures to update the safety criteria with regard for the actual operation experience, as a minimum, based on the actual reliability of the NPP unit personnel. The key components are presented for shaping the methodology to obtain the quantitative indicators of the personnel reliability based on data of the unit’s long-term actual operation experience. Recommendations and explanations are provided for each of the methodology’s key components, namely: an information model of the methodology, the key indicators and other components are provided. The timeliness of the methodology development is explained making it possible to obtain quantitative indicators based on the nuclear plant unit’s operation experience. An additional methodology is presented to assess the safety of nuclear power plants. A unique notional definition of the nuclear plant personnel reliability, and the procedures to justify the power unit safeguards with regard for the human factor aspects have been proposed. An information model of the methodology is provided and the prospects of its application to improve the safety justification procedure for various components of the nuclear plant units are described. To conclude with, ways are presented for the further evolution of the proposed methodology, and the scope of the methodology and the expected positive effect from its application are described.
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49

Denisova, L. A. "Automatic feed control of steam generator in the power unit of a nuclear power plant: Modeling and optimization." Automation and Remote Control 77, no. 6 (June 2016): 1084–92. http://dx.doi.org/10.1134/s00051179160600126.

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50

MATSUOKA, Tsuyoshi. "Analysis of Status Fourteen Hours after All Power Loss at the Fukushima Daiichi Nuclear Power Plant Unit 1." Transactions of the Atomic Energy Society of Japan 21, no. 1 (2022): 64–70. http://dx.doi.org/10.3327/taesj.j21.006.

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