Academic literature on the topic 'Marine nuclear reactor plants'

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Journal articles on the topic "Marine nuclear reactor plants"

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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 "Admiral Ushakov", 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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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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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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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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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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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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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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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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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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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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Dissertations / Theses on the topic "Marine nuclear reactor plants"

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Alam, Syed Bahauddin. "The design of reactor cores for civil nuclear marine propulsion." Thesis, University of Cambridge, 2018. https://www.repository.cam.ac.uk/handle/1810/275650.

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Perhaps surprisingly, the largest experience in operating nuclear power plants has been in nuclear naval propulsion, particularly submarines. This accumulated experience may become the basis of a proposed new generation of compact nuclear power plant designs. In an effort to de-carbonise commercial freight shipping, there is growing interest in the possibility of using nuclear propulsion systems. Reactor cores for such an application would need to be fundamentally different from land-based power generation systems, which require regular refueling, and from reactors used in military submarines,
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McKillop, Jordan M. "Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology." Thesis, Georgia Institute of Technology, 2009. http://hdl.handle.net/1853/37209.

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The main objective of this research is: (1) to develop a model and perform numerical simulations to evaluate the radiation field and the resulting dose to personnel and activation of materials and structures throughout the IRIS nuclear power plant, and (2) to confirm that the doses are below the regulatory limit, and assess the possibility to reduce the activation of the concrete walls around the reactor vessel to below the free release limit. IRIS is a new integral pressurized water reactor (PWR) developed by an international team led by Westinghouse with an electrical generation capacity of
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Foster, Jack Warren. "Development and implementation of a response-function concept for spent nuclear fuel cask analysis." Thesis, Georgia Institute of Technology, 1993. http://hdl.handle.net/1853/17275.

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Jourdan, Grégoire. "Using risk-based regulations for licensing nuclear power plants : case study of gas-cooled fast reactor." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/32278.

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Thesis (S.M.)--Massachusetts Institute of Technology, Engineering Systems Division, Technology and Policy Program, 2005.<br>Includes bibliographical references (p. 78-82).<br>The strategy adopted for national energy supply is one of the most important policy choice for the US. Although it has been dismissed in the past decades, nuclear power today has key assets when facing concerns on energy dependence and global warming. However, reactor licensing regulations need to be changed to get all the advantages of the most promising technologies. After reviewing the well-known drawbacks of the curre
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Khamis, Ibrahim Ahmad. "Simulation of nuclear power plant pressurizers with application to an inherently safe reactor." Diss., The University of Arizona, 1988. http://hdl.handle.net/10150/184378.

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Pressurizer modeling for predicting the dynamic pressure of the PIUS system is presented. The transient behavior of this model for the PIUS system was investigated. The validity of this model for the PIUS system is limited to transients that are neither too large nor too long in duration. For example, the model is not capable of describing events following a complete loss of liquid for the pressurizer. However, the model can be used for qualitative prediction of the PIUS system behavior for a wide variety of severe transients. A review of pressurizer modeling indicates that the neglecting of t
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Reperant, Jefferey John Robert. "Studies of turbulent liquid sheets for protecting IFE reactor chamber first walls." Thesis, Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/18921.

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Maples, Allen B. "Design of a robust acoustic positioning system for an underwater nuclear reactor vessel inspection robot." Thesis, This resource online, 1993. http://scholar.lib.vt.edu/theses/available/etd-06232009-063217/.

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Pounders, Justin Michael. "A coarse-mesh transport method for time-dependent reactor problems." Diss., Georgia Institute of Technology, 2010. http://hdl.handle.net/1853/39586.

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A new solution technique is derived for the time-dependent transport equation. This approach extends the steady-state coarse-mesh transport method that is based on global-local decompositions of large (i.e. full-core) neutron transport problems. The new method is based on polynomial expansions of the space, angle and time variables in a response-based formulation of the transport equation. The local problem (coarse mesh) solutions, which are entirely decoupled from each other, are characterized by space-, angle- and time-dependent response functions. These response functions are, in turn, used
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Sumner, Tyler Scott. "A safety and dynamics analysis of the subcritical advanced burner reactor: SABR." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24636.

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BRAGA, CLAUDIA C. "Analise de sensibilidade para modelagem semi-mecanistica de acidentes severos." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10399.

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Made available in DSpace on 2014-10-09T12:38:15Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:04:52Z (GMT). No. of bitstreams: 1 05655.pdf: 6224612 bytes, checksum: 86a04b4dcc94dbc7c8ce73759afdf4b2 (MD5)<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Books on the topic "Marine nuclear reactor plants"

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A, Kuznet͡sov V. Sudovye i͡adernye reaktory: Osnovy teorii i ėkspluatat͡sii. "Sudostroenie", 1988.

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Sarkisov, A. A. Osnovy teorii i ėkspluatat︠s︡ii sudovykh i︠a︡dernykh reaktorov. Nauka, 2008.

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Petrov, S. A. Sostoi︠a︡nie i perspektivy razvitii︠a︡ korabelʹnykh I︠A︡ĖU inostrannykh flotov. Sudostroenie, 2009.

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United States. Congress. House. Committee on Armed Services. Dept. of Energy, Defense Nuclear Facilities Panel., ed. Hearing on National Defense Authorization Act for fiscal years 1992 and 1993--H.R. 2100 and oversight of previously authorized programs before the Committee on Armed Services, House of Representatives, One Hundred Second Congress, first session: Seapower and Strategic and Critical Materials Subcommittee and Department of Energy Defense Nuclear Facilities Panel hearing on Naval Nuclear Propulsion Program : hearing held April 25, 1991. U.S. G.P.O., 1991.

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Doty, Carolyn Bailey. World commercial nuclear reactor business. Business Communications Co., 2002.

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Blake, E. Michael. U.S. power reactor performance, 1992-94. American Nuclear Society, 1995.

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Bullseye one reactor. House of Hits, 1987.

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International Atomic Energy Agency; IAEA. Design for reactor core safety in nuclear power plants. The Agency, 1986.

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Severe accidents in nuclear power plants. Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 1986.

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Beninson, D. Chernobyl reactor accident: Report of a consultation. World Health Organization, 1986.

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Book chapters on the topic "Marine nuclear reactor plants"

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Glasstone, Samuel, and Alexander Sesonske. "Advanced Plants and the Future." In Nuclear Reactor Engineering. Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-7525-2_15.

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Glasstone, Samuel, and Alexander Sesonske. "Advanced Plants and the Future." In Nuclear Reactor Engineering. Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-2083-2_8.

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Yu, Junchong. "Reactor Coolant System (RCS)." In Marine Nuclear Power Technology. Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-2894-1_3.

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Yu, Junchong. "Reactor Loading and Unloading." In Marine Nuclear Power Technology. Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-2894-1_17.

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Masterson, Robert E. "Natural Convection in Nuclear Power Plants." In Nuclear Reactor Thermal Hydraulics. CRC Press, 2019. http://dx.doi.org/10.1201/b22067-22.

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Masterson, Robert E. "Single-Phase Flow in Nuclear Power Plants." In Nuclear Reactor Thermal Hydraulics. CRC Press, 2019. http://dx.doi.org/10.1201/b22067-16.

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Masterson, Robert E. "Thermal Energy Production in Nuclear Power Plants." In Nuclear Reactor Thermal Hydraulics. CRC Press, 2019. http://dx.doi.org/10.1201/b22067-5.

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Masterson, Robert E. "Fundamentals of Two-Phase Flow in Nuclear Power Plants." In Nuclear Reactor Thermal Hydraulics. CRC Press, 2019. http://dx.doi.org/10.1201/b22067-23.

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Werner, W. F. "Mathematical Problems in the Simulation of Reactor Plants." In Nuclear Simulation. Springer Berlin Heidelberg, 1987. http://dx.doi.org/10.1007/978-3-642-83221-5_4.

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Masterson, Robert E. "Fundamentals of Single-Phase Heat Transfer in Nuclear Power Plants." In Nuclear Reactor Thermal Hydraulics. CRC Press, 2019. http://dx.doi.org/10.1201/b22067-20.

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Conference papers on the topic "Marine nuclear reactor plants"

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Khan, Salah Ud-din, Minjun Peng, Muhammad Zubair, and Shaowu Wang. "A Review on Specific Features of Small and Medium Sized Nuclear Power Plants." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29399.

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Due to global warming and high oil prices nuclear power is the most feasible solution for generating electricity. For the fledging nuclear power industry small and medium sized nuclear reactors (SMR’s) are instrumental for the development and demonstration of nuclear reactor technology. Due to the enhanced and outstanding safety features, these reactors have been considered globally. In this paper, first we have summarized the reactor design by considering some of the large nuclear reactor including advanced and theoretical nuclear reactor. Secondly, comparison between large nuclear reactors a
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Tilliette, Z. P. "Combined-Closed Gas Cycles for Terrestrial, Marine and Space Nuclear Power Systems." In ASME 1992 International Gas Turbine and Aeroengine Congress and Exposition. American Society of Mechanical Engineers, 1992. http://dx.doi.org/10.1115/92-gt-098.

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Higher temperature nuclear heat sources are becoming available and more efficient energy conversion systems can be proposed, namely Brayton-Rankine combined cycles which are presently very successful in the terrestrial fossil power plants market. A combined gas-steam cycle adaptation to the now being developed high temperature gas-cooled reactor MHTGR is presented. In order to avoid serious problems associated with the direct cycle, the concept features a He/He heat exchanger and a steam generator heated in series. Consequences are a significant plant efficiency increase, a sufficiently low re
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Vuorinen, Asko. "Conceptual Design of a 4 × 300 MW Modular Nuclear Plant." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6529.

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The Finnish companies have built four medium size nuclear power plants. In addition they have constructed two nuclear icebreakers and several floating power plants. The latest 1650 MWe nuclear power plant under construction Olkiluoto-3 has had many problems, which have raised the costs of the plant to €3500/kWe from its original estimate of €2000/kWe and constriction schedule from four to eight years. It is possible to keep the costs down and schedule short by making the plant in shipyard and transport it to site by sea. The plant could be then lifted to its place by pumping seawater into the
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Suzuki, Masaaki, Kazuyuki Demachi, Shigeru Takaya, and Yoshitaka Chikazawa. "Evaluation Method of Response Reliability During an Accident and its Applicability to Fast Reactor Plants." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82567.

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In this study, we develop new indices that evaluate the response capability — response margin and response reliability — of a nuclear power plant in case of occurrence of a severe accident by considering the ability of the nuclear power plant to recover system safety functions, which may have been affected by the accident, to the minimum safety values. Further, we demonstrate a specific evaluation procedure for our proposed indices. While performing the evaluation, we consider margins with respect to a minimum safety function level and a time constraint along with their temporal changes. Addit
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Peir, Jinn-Jer, Chun-Kuan Shih, Bau-Shei Pei, Yuh-Ming Ferng, and Wen-Sheng Hsu. "Power Uprate Impact Evaluations on Waste Heat of Nuclear Power Plants in Taiwan." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75885.

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Power uprate is currently being considered by several nuclear power plant (NPP) utilities as a way to improve plant economy since 1970s. In general there are three types of power uprate: measurement uncertainty recapture (&lt;2%), stretch power uprate (2 to 7%), and extended power uprate (7 to 20%). Prior to the uprate, a thorough evaluation of existing plant equipments and environmental impact must be assessed before a final decision and an optimal selection are made. Upon a power uprate, the power density and thermal release of a nuclear reactor would increase immediately, followed by the im
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Liu, Zhi-tong, Shao-ming Wang, Long-fei Zhang, Guang Yang, Meng Lv, and Hong-jian Zhang. "Digital Human-Machine Interface Design for Marine Nuclear Power Plant Based on Task-Oriented." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67244.

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A design of human machine interface (HMI) has been developed to ensure the safety and availability of marine nuclear power plant (NPP) in China. The staffing arrangement and HMIs are different from current nuclear power plants. One control room is used to monitor and control the reactor, the secondary loop, and the electric system. Considering the digital control room style, the elements of the HMIs in the control room are the large display panels and control consoles. Considering the digital control room style, the elements of the HMIs in the control room are the large display panels and cont
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Chen, Zhiyun, Wenzhen Chen, and Lei Luo. "Dynamic Simulation of Marine Nuclear Pressurizer." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29284.

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According to the specific structure of a marine reactor pressurizer and its operating characteristics of frequent pressure and water level fluctuation, a new non-equilibrium four region mathematical and physical model is established for the first time to fulfill the aim of fast and precise simulation. The model includes the bubble rising, condensate dropping, wall condensation and heat transfer through outside wall while the heat and mass transfer at the liquid and gas interface is neglected. The initializing program is also introduced. The Simulink is adopted as the simulating tool and the co
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Shukla, D. K. "Development of Surveillance and In-Service Inspection Programme for Indian Research Reactors Cirus and Dhruva." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89802.

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Many safety requirements for research reactors are quite similar to those of power reactors. For research reactors with a higher hazard potential, the use of safety codes and guides for power reactors is more appropriate. However, there are many important differences between power reactors and research reactors that must be taken into account to ensure that adequate safety margins are available in design and operation of the research reactor. Most research reactors may have small potential for hazard to the public compared to power reactors but may pose a greater potential hazard to the plant
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Sunder Raj, Komandur S. "Performance Considerations in Power Uprates of Nuclear Power Plants: A Case Study." In ASME 2005 Power Conference. ASMEDC, 2005. http://dx.doi.org/10.1115/pwr2005-50003.

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This paper examines the impact of power uprates on the performance of nuclear power plants. Since the 1970’s, power companies have been using power uprates to increase the output of their nuclear power plants. The plant systems and components should be capable of accommodating the accompanying increases in flow conditions. The affected components include the turbine-generator, pipes, valves, pumps, heat exchangers, electrical transformer, etc. The Nuclear Regulatory Commission has classified power uprates as falling into three categories: (1) measurement uncertainty recapture power uprates, (2
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Boonstra, H., A. C. Groot, and C. A. Prins. "On the Feasibility of Nuclear Versus Combustion Gas Turbine Propulsion for High-Speed Cargo Ships." In ASME Turbo Expo 2004: Power for Land, Sea, and Air. ASMEDC, 2004. http://dx.doi.org/10.1115/gt2004-53777.

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This paper presents the outcome of a study on the feasibility of a nuclear powered High-Speed Pentamaran, initiated by Nigel Gee and Associates and the Delft University of Technology. It explores the competitiveness of a nuclear power plant for the critical characteristics of a marine propulsion plant. Three nuclear reactor types are selected: the Pressurized Water Reactor (PWR), the Pebble-bed and Prismatic-block HTGR. Their characteristics are estimated for a power range from 100 MWth to 1000 MWth in a parametric design, providing a level base for comparison with conventional gas turbine tec
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Reports on the topic "Marine nuclear reactor plants"

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Palmiotti, G., J. Cahalan, P. Pfeiffer, et al. Requirements for advanced simulation of nuclear reactor and chemicalseparation plants. Office of Scientific and Technical Information (OSTI), 2006. http://dx.doi.org/10.2172/898579.

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Malinauskas, A. (Management of severe accidents at PWR (pressurized water reactor) nuclear power plants). Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6756735.

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Oxstrand, Johanna, Katya Le Blanc, and Aaron Bly. Light Water Reactor Sustainability Program: Computer-Based Procedures for Field Activities: Results from Three Evaluations at Nuclear Power Plants. Office of Scientific and Technical Information (OSTI), 2014. http://dx.doi.org/10.2172/1168650.

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Hsu, C. J., R. W. Youngblood, R. G. Fitzpatrick, and P. J. Amico. A probabilistic evaluation of the safety of Babcock and Wilcox nuclear reactor power plants with emphasis on historically observed operational events. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/6376138.

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Agarwal, Vivek, Pradeep Ramuhalli, Garill Coles, et al. Technical Specification Surveillance Interval Extension of Digital Equipment in Nuclear Power Plants: Review and Research. Light Water Reactor Sustainability Program report. Office of Scientific and Technical Information (OSTI), 2019. http://dx.doi.org/10.2172/1546735.

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Simmons, Kevin L., Pradeep Ramuhalli, David L. Brenchley, et al. Light Water Reactor Sustainability (LWRS) Program ? Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants. Office of Scientific and Technical Information (OSTI), 2012. http://dx.doi.org/10.2172/1097978.

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Szukiewicz, A. J. Regulatory analysis for resolution of USI (Unresolved Safety Issue) A-47: Safety implications of control systems in LWR (light-water reactor) nuclear power plants: Final report. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/5853094.

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Williams, Wesley. Regenerative Heater Optimization for Steam Turbo-Generation Cycles of Generation IV Nuclear Power Plants with a Comparison of Two Concepts for the Westinghouse International Reactor Innovative and Secure (IRIS). Office of Scientific and Technical Information (OSTI), 2002. http://dx.doi.org/10.2172/814139.

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United States Department of Energy`s reactor core protection evaluation methodology for fires at RBMK and VVER nuclear power plants. Revision 1. Office of Scientific and Technical Information (OSTI), 1997. http://dx.doi.org/10.2172/522199.

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