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Journal articles on the topic 'Marine nuclear reactor plants'

Author: Grafiati

Published: 4 June 2021

Last updated: 11 February 2022

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1

Хвостова and Marina Khvostova. "Engineering and Ecological Assessment of Nuclear Powered Ships Dismantling." Safety in Technosphere 4, no. 3 (2015): 3–11. http://dx.doi.org/10.12737/11874.

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The article considers basic approaches to dismantling of nuclear-powered guided missile heavy cruisers on the example of the nuclear-powered guided missile heavy cruiser &#34;Admiral Ushakov&#34;, as well as conceptual questions of safety during planned dismantling. The major factors that have impact on choosing the strategy of dismantling and on ensuring nuclear, radiation and ecological safety of the personnel, population and environment during dismantling are considered. The conclusion is that maintaining and servicing decommissioned nuclear powered ships and

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2

Szewczuk-Krypa, Natalia, Marta Drosińska-Komor, Jerzy Głuch, and Łukasz Breńkacz. "Comparison Analysis of Selected Nuclear Power Plants Supplied With Helium from High-Temperature Gas-Cooled Reactor." Polish Maritime Research 25, s1 (2018): 204–10. http://dx.doi.org/10.2478/pomr-2018-0043.

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Abstract The article presents results of efficiency calculations for two 560 MW nuclear cycles with high-temperature gas-cooled reactor (HTGR). An assumption was made that systems of this type can be used in so-called marine nuclear power plants. The first analysed system is the nuclear steam power plant. For the steam cycle, the efficiency calculations were performed with the code DIAGAR, which is dedicated for analysing this type of systems. The other system is the power plant with gas turbine, in which the combustion chamber has been replaced with the HTGR. For this system, a number of calc

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3

Sochinsky, S. "Ways to reduce metal consumption and welding scope for marine reactor containment." Transactions of the Krylov State Research Centre S-I, no. 2 (2020): 72–76. http://dx.doi.org/10.24937/2542-2324-2020-2-s-i-72-76.

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This paper discusses containment designs of nuclear icebreakers and floating power plants. The purpose of this work is to reduce metal consumption and scope of welding through development of a containment design with stressed state almost free of moments. This study justifies the possibility of lower metal consumption and welding scope through shifting from containment designs based on stiffened plates to the containments made up by cylindrical panels: optimal curvature of their surfaces will be obtained as per the theory of thin shells and will depend on the ratio between containment geometry

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4

Mitenkov, Feodor M., and Vitaly I. Polunichev. "Small nuclear heat and power co-generation stations and water desalination complexes on the basis of marine reactor plants." Nuclear Engineering and Design 173, no. 1-3 (1997): 183–91. http://dx.doi.org/10.1016/s0029-5493(97)00108-8.

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5

Gulliver, P., G. T. Cook, A. B. MacKenzie, P. Naysmith, and R. Anderson. "Sources of Anthropogenic 14C to the North Sea." Radiocarbon 46, no. 2 (2004): 869–75. http://dx.doi.org/10.1017/s0033822200035906.

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The Sellafield nuclear fuel reprocessing plant on the northwest coast of England is the largest source of anthropogenic radiocarbon to the UK coastal environment. In a mid-1990s study of 14C distribution around the UK coast, the pattern of dilution with increasing distance from Sellafield appeared to be perturbed by anomalously high 14C activities in marine biota in the coastal environment of northeast England. This present study was undertaken during 1998 and 1999 to determine whether this 14C enhancement was due to Sellafield or the nuclear power plants on the east coast. Seawater, seaweed (

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6

Wang, Ning, Chengde Shen, Weidong Sun, et al. "Seasonal 14C and Sr/Ca Records of a Modern Coral around Daya Bay Nuclear Power Plants." Radiocarbon 59, no. 3 (2017): 1035–46. http://dx.doi.org/10.1017/rdc.2017.43.

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ABSTRACTDue to an increasing number of nuclear reactors in operation, the radiocarbon (14C) released from nuclear power plants (NPPs) has become an important anthropogenic source of 14C. The examination of seasonal Δ14C and monthly Sr/Ca, Mg/Ca variations in a coral in Daya Bay (China) shows that NPPs located there have an impact on the Δ14C level and sea surface temperature (SST). The Mg/Ca variation was in good correlation with the Pacific Decadal Oscillation (PDO) before the operation of Ling’ao NPP in 2002, but this correlation became weak due to an abnormally higher SST after 2002. As ill

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7

Kusunoki, Tsuyoshi, Masahiko Kyouya, Hideo Kobayashi, and Masa-Aki Ochiai. "Simulation of a Marine Nuclear Reactor." Nuclear Technology 109, no. 2 (1995): 275–85. http://dx.doi.org/10.13182/nt95-a35060.

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8

Achkasov, A. N., E. V. Goltsov, G. I. Grechko, and Yu N. Kuznetsov. "Reactor facilities for small nuclear power plants." Atomic Energy 113, no. 1 (2012): 51–56. http://dx.doi.org/10.1007/s10512-012-9594-6.

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9

Petrunin, V. V. "Reactor Units for Small Nuclear Power Plants." Herald of the Russian Academy of Sciences 91, no. 3 (2021): 335–46. http://dx.doi.org/10.1134/s1019331621030126.

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10

Kudinovich, I., A. Suteeva, and V. Khoroshev. "Nuclear power plants for advanced civil marine technology." Transactions of the Krylov State Research Centre 4, no. 386 (2018): 95–106. http://dx.doi.org/10.24937/2542-2324-2018-4-386-95-106.

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11

Sevast’yanov, V. D., S. A. Nikolaev, I. E. Somov, V. F. Shikalov, and M. G. Mittel’man. "Research-reactor neutron fields for calibrating in-reactor detectors in nuclear power plants." Atomic Energy 100, no. 2 (2006): 96–103. http://dx.doi.org/10.1007/s10512-006-0056-x.

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12

Dong, Zhe, Miao Liu, Di Jiang, Xiaojin Huang, Yajun Zhang, and Zuoyi Zhang. "Automatic Generation Control of Nuclear Heating Reactor Power Plants." Energies 11, no. 10 (2018): 2782. http://dx.doi.org/10.3390/en11102782.

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A nuclear heating reactor (NHR) is a typical integral pressurized water reactor (iPWR) with advanced design features such as an integral primary circuit, self-pressurization, full-power-range natural circulation, and hydraulic control rods. Through adjusting its electric power output according to the variation of demand, NHR power plants can be adopted to stablize the fluctuation of grid frequency caused by the intermittent nature of renewable generation, which is useful for deepening the penetration of renewables. The flexibility of an NHR power plant relies on the automatic generation contro

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13

Kurnosov, V. A., Yu M. Simanovskii, Yu A. Khitrov, and E. N. Orekhov. "Conservation of reactor compartments of experimental nuclear power plants." Atomic Energy 80, no. 6 (1996): 422–26. http://dx.doi.org/10.1007/bf02415584.

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14

Gusev, B. A., I. S. Orlenkov, L. N. Moskvin, et al. "Experience in Decontamination of Naval Reactor Plants." Nuclear Technology 206, no. 5 (2019): 791–803. http://dx.doi.org/10.1080/00295450.2019.1693216.

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15

Balabin, V., M. Kamnev, N. Kuchin, O. Tyurikov, and A. Khizbullin. "Efficiency of emergency depressurization systems for marine nuclear reactor containments." Transactions of the Krylov State Research Centre 4, no. 386 (2018): 107–16. http://dx.doi.org/10.24937/2542-2324-2018-4-386-107-116.

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16

Fernández-Arias, Pablo, Diego Vergara, and José A. Orosa. "A Global Review of PWR Nuclear Power Plants." Applied Sciences 10, no. 13 (2020): 4434. http://dx.doi.org/10.3390/app10134434.

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Nuclear energy is presented as a real option in the face of the current problem of climate change and the need to reduce CO2 emissions. The nuclear reactor design with the greatest global impact throughout history and which has the most ambitious development plans is the Pressurized Water Reactor (PWR). Thus, a global review of such a reactor design is presented in this paper, utilizing the analysis of (i) technical aspects of the different variants of the PWR design implemented over the past eight years, (ii) the level of implementation of PWR nuclear power plants in the world, and (iii) a li

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17

UCHIDA, Shunsuke. "Water Chemistry of Light Water Cooled Reactor Plants⑴." Journal of the Atomic Energy Society of Japan 51, no. 2 (2009): 106–11. http://dx.doi.org/10.3327/jaesjb.51.2_106.

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18

NAITOH, Masanori. "Damage of Reactor Buildings at Fukushima Daiichi Nuclear Power Plants." Journal of the Atomic Energy Society of Japan 53, no. 7 (2011): 473–78. http://dx.doi.org/10.3327/jaesjb.53.7_473.

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19

Avramenko, A., M. Kovetska, A. Kravchuk, and Yu Kovetska. "Thermophysical Studies for Safety Assessment of Promising Nuclear Power Plants." Nuclear and Radiation Safety, no. 2(74) (May 22, 2017): 14–19. http://dx.doi.org/10.32918/nrs.2017.2(74).03.

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The paper describes the role of thermophysical studies for safety assessment and improvement of nuclear reactor technologies. The research considers the issues of using nanofluids for core cooling purposes and analyzes heat transfer problems in promising technologies of generation IV reactor designs with helium coolant and supercritical water. Besides, original results of calculations related to degraded heat transfer in seven-rod fuel assembly design with VVER-SKD geometrical parameters were presented.

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20

Naumov, Vadim, Sergey Gusak, and Andrey Naumov. "Small nuclear power plants for power supply in arctic regions: assessment of spent nuclear fuel radioactivity." Nuclear Energy and Technology 4, no. 2 (2018): 119–25. http://dx.doi.org/10.3897/nucet.4.30677.

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The purpose of the present study is the investigation of mass composition of long-lived radionuclides accumulated in the fuel cycle of small nuclear power plants (SNPP) as well as long-lived radioactivity of spent fuel of such reactors. Analysis was performed of the published data on the projects of SNPP with pressurized water-cooled reactors (LWR) and reactors cooled with Pb-Bi eutectics (SVBR). Information was obtained on the parameters of fuel cycle, design and materials of reactor cores, thermodynamic characteristics of coolants of the primary cooling circuit for reactor facilities of diff

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21

Buesseler, Ken, Michio Aoyama, and Masao Fukasawa. "Impacts of the Fukushima Nuclear Power Plants on Marine Radioactivity." Environmental Science & Technology 45, no. 23 (2011): 9931–35. http://dx.doi.org/10.1021/es202816c.

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22

Boothroyd, R. G. "Integrated molten-salt nuclear reactor systems for base-load power plants." International Journal of Energy Production and Management 2, no. 1 (2017): 39–51. http://dx.doi.org/10.2495/eq-v2-n1-39-51.

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23

Al-Mutaz, Ibrahim S. "Coupling of a nuclear reactor to hybrid RO-MSF desalination plants." Desalination 157, no. 1-3 (2003): 259–68. http://dx.doi.org/10.1016/s0011-9164(03)00405-3.

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24

Kilian, R., and A. Roth. "Corrosion behaviour of reactor coolant system materials in nuclear power plants." Materials and Corrosion 53, no. 10 (2002): 727–39. http://dx.doi.org/10.1002/1521-4176(200210)53:10<727::aid-maco727>3.0.co;2-#.

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25

Minehara, Eisuke J. "ICONE15-10634 FEASIBILITY OF LASER DECOMMSSIONING FOR NUCLEAR POWER REACTOR PLANTS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_347.

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26

Dragunov, Yu G., and V. P. Denisov. "Securing safe operation of VVÉR reactor systems in nuclear power plants." Atomic Energy 101, no. 2 (2006): 539–43. http://dx.doi.org/10.1007/s10512-006-0127-z.

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27

Wang, Liang, Yantao Shi, Xiaogong Bai, et al. "From marine plants to photovoltaic devices." Energy Environ. Sci. 7, no. 1 (2014): 343–46. http://dx.doi.org/10.1039/c3ee42767f.

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28

Vergara, Julio A., and Chris B. McKesson. "Marine Technology Nuclear Propulsion in High-Performance Cargo Vessels." Marine Technology and SNAME News 39, no. 01 (2002): 1–11. http://dx.doi.org/10.5957/mt1.2002.39.1.1.

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It has been about 40 years since nuclear-powered merchant ships were seriously discussed in the naval architecture community. But recent developments in commercial shipping include bigger, faster, and more powerful ships, where nuclear propulsion may be an option worth considering. The development of advanced ship designs opens an opportunity for high-speed maritime transportation that could create new markets and recover a fraction of the high value goods currently shipped only by air. One of the vessels being considered is FastShip, a large monohull ship that would require 250 MW in 5 gas tu

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29

Kusunoki, T., N. Odano, T. Yoritsune, T. Ishida, T. Hoshi, and K. Sako. "Design of advanced integral-type marine reactor, MRX." Nuclear Engineering and Design 201, no. 2-3 (2000): 155–75. http://dx.doi.org/10.1016/s0029-5493(00)00285-5.

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30

Lyu, Xuefeng, Shuai Liu, Ke Ji, Yang Feng, Shengfei Wang, and Zhichao Huang. "Research on hydrogen risk and hydrogen control system in marine nuclear reactor." Annals of Nuclear Energy 141 (June 2020): 107373. http://dx.doi.org/10.1016/j.anucene.2020.107373.

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31

ARITA, Setsuo, Tetsuo ITO, Atomi NOGUCHI, and Fumio MURATA. "Reliability Enhancement of Reactor Protection System for BW R Plants." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 34, no. 5 (1992): 444–54. http://dx.doi.org/10.3327/jaesj.34.444.

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32

Szewczuk-Krypa, Natalia, Anna Grzymkowska, and Jerzy Głuch. "Comparative Analysis of Thermodynamic Cycles of Selected Nuclear Ship Power Plants With High-Temperature Helium-Cooled Nuclear Reactor." Polish Maritime Research 25, s1 (2018): 218–24. http://dx.doi.org/10.2478/pomr-2018-0045.

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Abstract This paper presents a comparative analysis of thermodynamic cycles of two ship power plant systems with a high-temperature helium-cooled nuclear reactor. The first of them is a gas system with recuperator, in which classical gas chamber is substituted for a HTGR reactor (High Temperature Gas-cooled Reactor). The second of the considered cycles is a combined gas-steam system where working medium flux from gas turbine outlet is directed into waste heat boiler and its heat is utilized for production of superheated steam to drive steam turbine. Preliminary calculations of the combine cycl

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33

Kaiser, Jan Christian. "Empirical Risk Analysis of Severe Reactor Accidents in Nuclear Power Plants after Fukushima." Science and Technology of Nuclear Installations 2012 (2012): 1–6. http://dx.doi.org/10.1155/2012/384987.

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Many countries are reexamining the risks connected with nuclear power generation after the Fukushima accidents. To provide updated information for the corresponding discussion a simple empirical approach is applied for risk quantification of severe reactor accidents with International Nuclear and Radiological Event Scale (INES) level≥5. The analysis is based on worldwide data of commercial nuclear facilities. An empirical hazard of 21 (95% confidence intervals (CI) 4; 62) severe accidents among the world’s reactors in 100,000 years of operation has been estimated. This result is compatible wit

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34

FUJISHIRO, Toshio. "What Happened in the Reactor Fuels of Fukushima Daiichi Nuclear Power Plants." Journal of the Atomic Energy Society of Japan 53, no. 8 (2011): 550–54. http://dx.doi.org/10.3327/jaesjb.53.8_550.

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35

Fukunishi, Kohyu, and Satoshi Suzuki. "Real-Time Stability Monitoring Method for Boiling Water Reactor Nuclear Power Plants." Nuclear Technology 78, no. 2 (1987): 132–39. http://dx.doi.org/10.13182/nt87-a33991.

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36

Egorov, K. E., and N. S. Sokolov. "Characteristic features of bed deformation under reactor compartments at nuclear power plants." Soil Mechanics and Foundation Engineering 22, no. 4 (1985): 135–40. http://dx.doi.org/10.1007/bf01964395.

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37

Gutsalov, A. T., V. S. Ionov, M. I. Miroshnichenko, and N. I. Sulkhanishvili. "The modern concept of the Nuclear Safety Code for Atomic Reactor Plants." Soviet Atomic Energy 69, no. 6 (1990): 1009–13. http://dx.doi.org/10.1007/bf02044637.

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38

Mityaev, Yu I., Yu I. Tokarev, I. N. Sokolov, �. �. Pakkh, and V. I. Abramov. "New generation of boiling-water-reactor nuclear power plants of increased safety." Atomic Energy 73, no. 1 (1992): 558–63. http://dx.doi.org/10.1007/bf00749525.

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39

Bakhracheva, Yulia S. "Influence of irradiation on the dynamics of changes in the mechanical properties of the nuclear reactor vessel." MATEC Web of Conferences 226 (2018): 01024. http://dx.doi.org/10.1051/matecconf/201822601024.

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Nuclear power plants are important generating units of the energy system worldwide. In the normal mode, nuclear power plants are absolutely safe, but emergency systems with radiation emissions have a devastating impact on the environment and public health. Despite the introduction of technologies and automatic monitoring systems, the threat of a potentially dangerous situation remains. The reactor vessel is the main object of activities to ensure the safety of nuclear power plants. One of the problems of ensuring the safety of nuclear power plant reactor vessels is the prediction of the level

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40

Fukutomi, Shigeki, Yukio Takigawa, and Hideaki Namba. "Operational Margin Monitoring System for Boiling Water Reactor Power Plants." Nuclear Technology 100, no. 1 (1992): 13–24. http://dx.doi.org/10.13182/nt92-a34750.

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41

Dong, Zhe, Yifei Pan, Maoxuan Song, Xiaojing Huang, Yujie Dong, and Zuoyi Zhang. "Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant." Science and Technology of Nuclear Installations 2017 (2017): 1–19. http://dx.doi.org/10.1155/2017/6298037.

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The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) with inherent safety feature. Due to its high reactor outlet coolant temperature, the MHTGR can be applied not only for electricity production but also as a heat source for industrial complexes. Through multimodular scheme, that is, the superheated steam flows produced by multiple MHTGR-based nuclear supplying system (NSSS) modules combined together to drive a common thermal load, the inherent safety feature of MHTGR is applicable to large-scale nuclear plants at any desired power ratings. Since th

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42

Moray, Neville, John Lee, Kim J. Vicente, Barclay G. Jones, and Jens Rasmussen. "A Direct Perception Interface for Nuclear Power Plants." Proceedings of the Human Factors and Ergonomics Society Annual Meeting 38, no. 9 (1994): 481–85. http://dx.doi.org/10.1177/154193129403800905.

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Following the suggestions of Beltracchi (1987) a direct perception interface for the thermal hydraulic systems of a pressurized water nuclear power reactor (PWR) was developed. It presents operators with an animated graphic of the Rankine heat cycle describing the functional relations of steam generation in a PWR. The ability of students of thermal and nuclear systems to recall system states, and detect and diagnose nine transients was compared to that of experienced nuclear power plant operators. The results were compared to a display representing traditional analog meters. The direct percept

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43

Ishida, I., T. Kusunoki, H. Murata, T. Yokomura, M. Kobayashi, and H. Nariai. "Thermal-hydraulic behavior of a marine reactor during oscillations." Nuclear Engineering and Design 120, no. 2-3 (1990): 213–25. http://dx.doi.org/10.1016/0029-5493(90)90374-7.

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44

Xu, Li, Ru Chao Deng, Chu Xu, Di Zhang, and Chen Xing Sheng. "Safety Study of Primary Loop System of Civil Marine Nuclear Power Plant." Applied Mechanics and Materials 541-542 (March 2014): 916–21. http://dx.doi.org/10.4028/www.scientific.net/amm.541-542.916.

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For evaluate the risk of civil marine nuclear power plant, through the searching related standards for ship, external environmental parameters that the nuclear ship should be suited was found. Based on the characteristics of power plant of civil nuclear-powered ship, the hierarchy system of primary loop system was established and corresponding indicator marking criteria were formulated for the risk assessment. The result shows that the Reactor Safety Injection System (RIS), the Reactor Boron and the Water Supply System (REA), the Control Rods and the Hull of Fuel Canning are the key risk facto

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45

Schumm, Andreas, Madalina Rabung, Gregory Marque, and Jary Hamalainen. "Reactor performance, system reliability, instrumentation and control." EPJ Nuclear Sciences & Technologies 6 (2020): 43. http://dx.doi.org/10.1051/epjn/2019017.

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We present a cross-cutting review of three on-going Horizon 2020 projects (ADVISE, NOMAD, TEAM CABLES) and one already finished FP7 project (HARMONICS), which address the reliability of safety-relevant components and systems in nuclear power plants, with a scope ranging from the pressure vessel and primary loop to safety-critical software systems and electrical cables. The paper discusses scientific challenges faced in the beginning and achievements made throughout the projects, including the industrial impact and lessons learned. Two particular aspects highlighted concern the way the projects

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46

Esmail, Shadwan M. M., and Jae Hak Cheong. "Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool." Science and Technology of Nuclear Installations 2021 (May 3, 2021): 1–26. http://dx.doi.org/10.1155/2021/8818479.

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An optimal long-term electric power strategy for Saudi Arabia to adopt nuclear power was evaluated using the MESSAGE tool. Saudi Arabia is predicted to experience an electricity shortage by 2025 with the present energy system. This electricity shortage could be postponed until 2035 by rehabilitating the existing power plants. The MESSAGE model predicts that adopting a combination of renewable (i.e., solar and wind), advanced traditional power (i.e., gas turbine, steam, and combined cycle), and nuclear technologies is the most competitive future strategy to supply 43.7%, 41.6%, and 3.8%, respec

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47

Zhao, Huijing, Guanhui Zhao, and Rui Ma. "A study on auxiliary steam reducing device in marine nuclear power plants." IOP Conference Series: Materials Science and Engineering 740 (March 17, 2020): 012033. http://dx.doi.org/10.1088/1757-899x/740/1/012033.

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48

Masson, M., G. Gontier, and L. Foulquier. "Radioecological Impact of the French Nuclear Power Plants on the Marine Environment." Radiation Protection Dosimetry 75, no. 1 (1998): 167–70. http://dx.doi.org/10.1093/oxfordjournals.rpd.a032222.

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49

Petrochenko, V. V., S. A. Grigoriev, A. V. Dedul, O. G. Komlev, A. V. Kondaurov, and G. I. Toshinsky. "Nuclear power plants of low and medium power with SVBR-100 reactor facilities." Journal of Physics: Conference Series 1475 (March 2020): 012014. http://dx.doi.org/10.1088/1742-6596/1475/1/012014.

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50

Koomey, Jonathan, and Nathan E. Hultman. "A reactor-level analysis of busbar costs for US nuclear plants, 1970–2005." Energy Policy 35, no. 11 (2007): 5630–42. http://dx.doi.org/10.1016/j.enpol.2007.06.005.

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