Academic literature on the topic 'Floating Nuclear Power'
Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles
Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Floating Nuclear Power.'
Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.
You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.
Journal articles on the topic "Floating Nuclear Power"
1
Verma, S. S. "Floating nuclear power plants." International Journal of Nuclear Desalination 2, no. 4 (2007): 311. http://dx.doi.org/10.1504/ijnd.2007.015798.
Full text
2
Alvin Toh, Yew Seng, and Andrew Palmer. "Floating nuclear power for Singapore." IES Journal Part A: Civil & Structural Engineering 7, no. 2 (March 19, 2014): 121–25. http://dx.doi.org/10.1080/19373260.2014.886986.
Full text
3
Kuznecov, V., O. Kondrat'eva, S. Priymak, K. Ceytin, and E. Yurchevskiy. "Ensuring of Nuclear, Radiation and Environmental Safety for a Floating Nuclear Power Plant based on KLT‑40S Reactor Installations." Safety in Technosphere 9, no. 2 (March 16, 2021): 10–19. http://dx.doi.org/10.12737/1998-071x-2021-9-2-10-19.
Full textAbstract:
Main principles and criteria for nuclear and radiation safety of a floating nuclear power plant have been considered. It has been shown that the existing regulatory framework, technical and organizational safety measures for nuclear and radiation safety of a floating nuclear power plant are sufficient, and operation of the floating nuclear power plant won't lead to an irradiation of the population above recommended norms both at its normal work, and in case of project accidents and under-project ones.
4
Zou, Shuliang, Na Liu, and Binhai Huang. "Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident." Science and Technology of Nuclear Installations 2021 (September 1, 2021): 1–8. http://dx.doi.org/10.1155/2021/1299821.
Full textAbstract:
Floating nuclear power plant is a kind of nuclear power plant on a barge moored specifically in an area of the sea. In order to study the factors influencing airborne radionuclide dispersion induced by the loss-of-coolant accident in floating nuclear power plant, the floating nuclear power plant platform was taken as the research object, and the dispersion of airborne radionuclide under combined conditions of platform positions, wind directions, and break directions (north, south, west, and east) was simulated by the CFD (computational fluid dynamics) method. The results show that northern and southern breaks have less dangerous island area than western and eastern ones but have more platform dangerous area than the western and eastern ones. The risk of the southern break is the greatest, and that of the western break is the least. Rotating the floating nuclear power plant platform in a certain angle can reduce the damage of loss-of-coolant accident. The effects of the dose received by the personnel under the condition of the severe accident were evaluated based on previous research, showing that the inhalation effective dose and the effective dose of plume immersion exposure were less than the radiation dose limit of 0.25 Sv within two hours in the accident. The results of the study can provide reference for the design of floating nuclear power plant platform and the formulation of emergency plan.
5
Tupchienko, V. A., and H. G. Imanova. "Nuclear icebreaker fleet and power supply on the basis of floating power units." Voprosy regionalnoj ekonomiki 35, no. 4 (December 30, 2018): 110–13. http://dx.doi.org/10.21499/2078-4023-2018--4-110-113.
Full textAbstract:
The article deals with the problem of the development of the domestic nuclear icebreaker fleet in the context of the implementation of nuclear logistics in the Arctic. The paper analyzes the key achievements of the Russian nuclear industry, highlights the key areas of development of the nuclear sector in the Far North, and identifies aspects of the development of mechanisms to ensure access to energy on the basis of floating nuclear power units. It is found that Russia is currently a leader in the implementation of the nuclear aspect of foreign policy and in providing energy to the Arctic region.
6
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.
Full textAbstract:
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.
7
Lysenko M, M. N., V. M. Bedenko, and F. Dalnoki-Veress. "Legal Regulations of Floating Nuclear Power Plants: problems and prospects." Moscow Journal of International Law 2019, no. 3 (September 28, 2019): 59–67. http://dx.doi.org/10.24833/0869-0049-2019-3-59-67.
Full text
8
Korolev, Vladimir I. "Rapid preliminary modeling of transport reactor cores." Nuclear Energy and Technology 7, no. 1 (March 30, 2021): 41–47. http://dx.doi.org/10.3897/nucet.7.65310.
Full textAbstract:
At the present time, JSC Baltiskiy zavod has built and transported to the deployment site at Pevek Akademik Lomonosov, a floating nuclear power unit (FNPU), project 20870. There are also three multi-purpose nuclear icebreakers of project 22220 (Arktika, Sibir, Ural) under construction at Baltiskiy being at different readiness stages. A decision has been made to build a nuclear icebreaker, Lider, of even a higher power. Integral reactors developed by JSC OKBM Afrikantov are installed in the nuclear icebreakers using new assembly-type cores which have not been used earlier in floating facilities. A great deal of preliminary calculation is required to give these cores as advantageous characteristics as possible. The paper proposes a procedure for rapid modeling of floating cores with varied operating and design characteristics. This procedure can be used as part of preliminary modeling. The procedure is based on using a combined dimensionless parameter proposed by the author in (Korolev 2009). A chart is presented to model the key performance of cores for floating objects with a nuclear reactor NPPs. Eight assembly-type core options, which can be installed in transport reactors of a modular or integral design, are analyzed.
9
Myasnikov, Yurij, and Vitalij Horoshev. "Technology of diagnostic assurance of the floating thermal nuclear power plant." Arctic: Ecology and Economy, no. 3(27) (September 14, 2017): 69–85. http://dx.doi.org/10.25283/2223-4594-2017-3-69-85.
Full text
10
ZHOU, Bingyan, Danrong SONG, Zhang CHEN, Xiaoming CHAI, Hongzhi XIANG, and Yuying HU. "A COMBINED REACTIVITY CONTROL PATTERN ON A FLOATING NUCLEAR POWER PLANT." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27 (2019): 1121. http://dx.doi.org/10.1299/jsmeicone.2019.27.1121.
Full textDissertations / Theses on the topic "Floating Nuclear Power"
1
Strother, Matthew Brian. "Hydrodynamic analysis of the offshore floating nuclear power plant." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/100112.
Full textAbstract:
Thesis: Nav. E., Massachusetts Institute of Technology, Department of Mechanical Engineering, 2015.Thesis: S.M. in Engineering and Management, Massachusetts Institute of Technology, Engineering Systems Division, 2015.
Cataloged from PDF version of thesis.
Includes bibliographical references (pages 85-86).
Hydrodynamic analysis of two models of the Offshore Floating Nuclear Plant [91 was conducted. The OFNP-300 and the OFNP-1100 were both exposed to computer simulated sea states in the computer program OrcaFlex: first to sets of monochromatic waves, each consisting of a single frequency and waveheight, and then to Bretschneider and JONSWAP spectra simulating 100-year storms in, respectively, the Gulf of Mexico and the North Sea. Hydrodynamic coefficients for these simulations were obtained using a separate computer program, WAMIT. Both models exhibited satisfactory performance in both heave and pitch. An alternative design of the OFNP-300 was developed and similarly analyzed in attempt to further improve hydrodynamic performance. A catenary mooring system was designed and analyzed for both plant models. The number of chains and the length of each were selected to ensure the mooring systems would withstand, with sufficient margins of safety, the maximum tension produced in a 100-year storm. This analysis was conducted both with all the designed mooring lines intact, and with the worst-case line broken. A lifecycle cost analysis of various mooring systems was conducted in order to minimize the cost of the mooring system while maintaining adequate performance.
by Matthew Brian Strother.
Nav. E.
S.M. in Engineering and Management
2
Jurewicz, Jacob M. "Design and construction of an offshore floating nuclear power plant." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/103707.
Full textAbstract:
Thesis: S.M. and S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015.Cataloged from PDF version of thesis.
Includes bibliographical references (pages 135-138).
This thesis details the ongoing development of a new Offshore Floating Nuclear Plant (OFNP) concept that exhibits a promising potential for economic and rapid deployment on a global scale. The OFNP creatively combines state-of-the-art Light Water Reactors (LWRs) and floating platforms similar to those used in offshore oil and gas operations. A reliable and cost-effective global supply chain exists for both technologies, which enables a robust expansion in the use of nuclear energy on a time scale consistent with combating climate change in the near future. The OFNP is a plant that can be entirely built within a floating platform in a shipyard, transferred to the site, where it is anchored within 12 nautical miles (22 km) off the coast in relatively deep water (=/> 100 m), and connected to the grid via submarine AC transmission cables. Shipyard construction ensures a supply of qualified workers and facilities, and it brings mass-production-like construction efficiency to existing reactor designs. Eventual shipyard decommissioning allows sites to immediately return to a "green field" condition when the plant's life is spent. The crews would operate in monthly or semi-monthly shifts with onboard living quarters, similar to oil and gas platforms. The OFNP is a nuclear plant specifically designed for the global market: it can be constructed in one country or multiple countries and exported internationally. It lends itself to a flexible and mobile electricity generation strategy, which minimizes the need for indigenous nuclear infrastructure in the host country and does not commit the customer to a 40 to 60 years-long project.
by Jacob M. Jurewicz.
S.M. and S.B.
3
Briccetti, Angelo (Angelo J. ). "An analysis of the spreading of radionuclides from a vent of an offshore floating nuclear power plant." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/115452.
Full textAbstract:
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015."June 2015." Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 70-71).
The offshore floating nuclear power plant (OFNP), is a new power plant design which provides for both increased safety and extra barriers to separate its radioactive material from the public. This design will minimize the probability of a severe accident leading to a release of radioactive material, but as always a release must still be planned for. The offshore siting of an OFNP allows for increased distance to human populations in addition to extra filtering of released radioactive material. This study will look at the potential consequences of a severe accident onboard an OFNP eventually leading to a vent and environment contamination. Three steps of the accident and fallout will be analyzed: 1) Accident and vent composition 2) The transport of radioactive material in the ocean via a plume and ocean diffusion 3) Sedimentation of radioactive cesium on the coast One of the major advantages of an OFNP over a terrestrial plant is that the extra distance and barriers provided by the OFNP will decrease the impact of a nuclear accident. This study will begin to quantify that effect. This is only the first attempt at exploring the effects of a release, and has large conservatisms built into the analysis even in the best estimate case. In the future more detailed work will be done to reach a more accurate solution, particularly for specific siting locations.
by Angelo Briccetti.
S.M.
4
Ford, Michael J. "Studies in Nuclear Energy: Low Risk and Low Carbon." Research Showcase @ CMU, 2017. http://repository.cmu.edu/dissertations/872.
Full textAbstract:
The amount of greenhouse gas emissions mitigation required to prevent the most dramatic climate change scenarios postulated in the 2014 IPCC Synthesis Report is substantial. Prior analyses have examined the potential for nuclear energy to play a role in decarbonizing the energy sector, one of the largest contributors to emissions worldwide. However, advanced, non-light water reactors, while often touted as a viable alternative for development, have languished. Large light water development projects have a repeated history of extended construction timelines, re-work delays, and significant capital risk. With few exceptions, large-scale nuclear projects have demonstrated neither affordability nor economic competitiveness, and are not well suited to nations with smaller energy grids, or to replace fossil generation in the industrial process heat sector. If nuclear power is to play a role in decarbonization, new policy and technical solutions will be needed. In this manuscript, we examine key aspects of past performance across the nuclear enterprise and explore the future potential of nuclear energy worldwide, focusing on policy and technical solutions that may be needed to move nuclear power forward as a part of a low-carbon energy future. We do so first at a high level, examining the history of nuclear power research and development in the United States, the nation that historically has led the way in the development of this generating technology. A significant portion of our analysis is focused on new developments in this technology – advanced non-light water reactors and small modular reactors. We find that while there are promising technical solutions available, improved funding and focus in research and new models of deployment may be needed if nuclear is to play a continuing or future role. We also find that in examining potential new markets for the technology, a continuing focus on institutional readiness is critical.
5
Itiki, Rodney. "Metodologia para mapeamento de zonas operacionais em sistemas de transmissão VSC-HVDC." Universidade de São Paulo, 2018. http://www.teses.usp.br/teses/disponiveis/3/3143/tde-09042018-145504/.
Full textAbstract:
Sistemas de transmissão de energia elétrica em corrente contínua e alta tensão baseados em tecnologia de conversores a fonte de tensão (VSC-HVDC), ao contrário de linhas de transmissão em corrente alternada, operam como elementos de controle de variáveis elétricas, podendo ser úteis na estabilidade do sistema de potência. Mas apesar desta vantagem, sistemas VSC-HVDC possuem limitações no desempenho estável, o que enseja o desenvolvimento de uma metodologia para mapeamento de suas zonas de operação estável e possíveis regiões de instabilidade. Inicialmente estudou-se os detalhes da tecnologia VSC-HVDC tais como o funcionamento da eletrônica de potência e estratégias de controle utilizadas. Em seguida, investigou-se os modelos de geradores síncronos para interconexão com o lado CA das estações conversoras do VSC-HVDC. E, finalmente, aplicou-se a tecnologia VSC-HVDC sobre um modelo de sistema de potência com uma estação conversora localizada em um porto offshore e uma outra no continente, próxima à rede de alta tensão em corrente alternada. Simulações e análise deste sistema foram executadas considerando várias condições operacionais. O gráfico de potência gerada e consumida, obtido pela aplicação da metodologia, apresenta grande potencial de uso prático como por exemplo sua implementação na interface homem-máquina da estação de operação do porto offshore, provendo informação em tempo real de alto nível ao operador do sistema elétrico do porto offshore e consequentemente aumentando sua consciência situacional quanto a proximidade dos limites de instabilidade.High voltage direct current power transmission systems based on voltage source converters (VSC-HVDC), as opposed to alternating current ones, operates as elements of control of electrical variables, being useful for stability of power system. Besides this advantage, VSC-HVDC systems have limitations in stable performance, which instigates the development of a methodology for mapping its operational zones of stability and possible regions of instability. The author initially studied the details of the VSC-HVDC technology such as the power electronic principles and the control strategies used on this research. Subsequently, the author investigated synchronous generator models for interconnection on the AC side of the VSC-HVDC converter stations. Finally, the author applied the VSC-HVDC technology on a model of power system with two converter stations, one located on an offshore port and the other on the shore, next to an alternating current high voltage power grid. Simulations and analysis of this system were carried out considering various operational conditions. The graphic of generated and consumed power on offshore port, obtained by the application of the methodology for mapping operational zones, presents a great potential of being implemented in the man-machine interface of an operation workstation, thus providing high level online information for the operator of the offshore port electrical system and consequently improving its situational awareness of the proximity to instability limits.
Book chapters on the topic "Floating Nuclear Power"
1
Subki, M. Hadid. "Floating Nuclear Power Plants With Small Modular Reactors." In Encyclopedia of Nuclear Energy, 711–20. Elsevier, 2021. http://dx.doi.org/10.1016/b978-0-12-819725-7.00226-9.
Full text
2
Avery, William H., and Chih Wu. "OTEC Closed-Cycle Systems Cost Evaluation." In Renewable Energy from the Ocean. Oxford University Press, 1994. http://dx.doi.org/10.1093/oso/9780195071993.003.0014.
Full textAbstract:
Innovative technologies such as OTEC achieve commercial development when potential investors decide that the return on the investment will repay the estimated development costs plus a profit, with an acceptably low risk of cost overruns. Industrial experience shows that the estimated cost to complete development of a new technology generally increases as development proceeds from the conceptual design through pilot development, demonstration, field testing, and final commercial manufacture (Merrow et al., 1981). The ratio between final cost and initial design estimate is strongly dependent on the extent to which the manufacturing process employs already developed equipment, procedures, and facilities. New projects that require “high technology” for their success, such as jet engines or nuclear power plants, have been characterized by large underestimates of the final costs, whereas the costs of projects that are firmly based on existing technology, such as the development of “supertankers,” have been accomplished well within the usual industrial uncertainty margin of ± 15 to 20%. The accuracy of the estimate is also strongly dependent on the thoroughness of the systems engineering evaluation that is done before development proceeds. Commercial applications of OTEC have been proposed in three principal categories. The first includes OTEC power plants mounted on floating platforms that would generate 50- to 400 MWe (net) of onboard electric power. The need to minimize plant size makes it mandatory to use closed-cycle OTEC for these applications. The second category includes land-based or shelf-mounted plants designed to supply power in the 50- to 400-MWe range to municipal utilities. Either open- or closed-cycle systems could be suitable. The third category comprises small (5- to 20-MWe) land-based or shelf-mounted OTEC plants designed for island applications where electric power generation, mariculture, fresh-water production, supply of cold water for air-conditioning systems, and fuel production could be combined to offer an economically attractive OTEC system despite the relatively high cost of power for small OTEC installations. Open-cycle OTEC plants may be the preferred choice for the third category. The estimated investment costs of installed complete OTEC systems, measured in dollars per kilowatt of net OTEC electric power generated, differ significantly among the three categories.
Conference papers on the topic "Floating Nuclear Power"
1
Bai, Fan, Yong Liu, Xingsheng Lao, Qi Xiao, Zhenxing Zhao, Jun Wu, Can Ma, and Wang Wei. "LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82180.
Full textAbstract:
Floating nuclear power stations are vessels with nuclear reactors, designed to power offshore oil and gas drilling, island development and remote areas. The safety of the facilities is an important issue. The Leak-Before-Break (LBB) assessment is essential to the design and evaluation of nuclear power plants against a sudden double-ended guillotine break of pipes. This paper describes the LBB assessment procedure applicable to the nuclear-class pipe of the floating nuclear power station. The loads considered in the analysis include variation of temperature/pressure, swing and underwater impact. Circumferential cracks are postulated at the dangerous positions of the pipe. The fatigue propagation of the surface crack is predicted based on the fracture mechanics and the finite element method to determine the time that pipe leaking happens. The critical length of the through-wall crack is calculated by the J integral–tearing modulus approach, and then compared with the minimum detectable crack length for the purpose that unstable fracture would not be happened before the leakage detected. According to the results of the analysis it could conclude that the pipe fulfils the LBB requirements.
2
Kuznetsov, Yu N., B. A. Gabaraev, V. A. Reshetov, and V. A. Moskin. "Leasing of Nuclear Power Plants With Using Floating Technologies." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22186.
Full textAbstract:
The proposal to organize and realize the international program on leasing of Nuclear Power Plant (NPP) reactor compartments is brought to the notice of potential partners. The proposal is oriented to the construction of new NPPs or to replacement of worked-out reactor units of the NPPs in operation on the sites situated near water area and to the use of afloat technologies for construction, mounting and transportation of reactor units as a Reactor Compartment Block Module (RCBM). According to the offered project the RCBM is fabricated in factory conditions at the largest Russian defense shipbuilding plant — State Unitary Enterprise “Industrial Association SEVMASHPREDPRIYATIE” (SEVMASH) in the city of Severodvinsk of the Arkhangelsk region. After completion of assembling, testing and preliminary licensing the RCBM is given buoyancy by means of hermetic sealing and using pontoons and barges. The RCBM delivery to the NPP site situated near water area is performed by sea route. The RCBM is brought to the place of its installation with the use of appropriate hydraulic structures (canals, shipping locks), then is lowered on the basement constructed beforehand and incorporated into NPP scheme, of which the components are installed in advance. Floating means can be detached from the RCBM and used repeatedly for other RCBMs. Further procedure of NPP commissioning and its operation is carried out according to traditional method by power company in the framework of RCBM leasing with enlisting the services of firm-manufacturer’s specialists either to provide reactor plant operation and concomitant processes or to perform author’s supervision of operation. After completion of lifetime and reactor unloading the RCBM is dismantled with using the same afloat technology and taken away from NPP site to sea area entirely, together with its structures (reactor vessel, heat exchangers, pumps, pipelines and other equipment). Then RCBM is transported by shipping route to a firm-manufacturer, for subsequent reprocessing, utilization and storage. Nuclear fuel and radioactive wastes are removed from NPP site also. Use of leasing method removes legal problems connected with the transportation of radioactive materials through state borders as the RCBM remains a property of the state-producer at all stages of its life cycle.
3
Wan, Lei, Guiyong Li, Min Rui, Yongkang Liu, and Jue Yang. "Study on Supervision Mode of Floating Nuclear Power Plant With Small Modular Reactor." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82138.
Full textAbstract:
A floating nuclear power plant (FNPP) with small modular reactor (SMR) is a combination of a civilian nuclear infrastructure and an offshore installation, which is defined as a floating nuclear facility. The article draws the lessons from studying of the engineer combination like Floating Production Storage and Offloading (FPSO) under the regulation of several government departments. It puts forward recommendations for license application and government regulation as follows in consideration with current license application for nuclear power plant and ship survey. A FNPP shall follow the requirements of construction, fueling and operation for civil nuclear installation combined with ship survey. Application is submitted to nuclear safety regulator for construction permit, while the design drawings shall be submitted to department of ship survey which checks the drawings whether meet the requirements of ship survey, considering some nuclear safety needs. The result of ship survey shall be represented in the safety analysis reports. The construction and important devices manufacturing shall be under the supervision of nuclear installation regulators and ship survey departments. In conclusion, National Nuclear Safety Administration (NNSA) and Maritime Safety Administration of the People’s Republic of China (MSA) shall establish united supervisory system for SMR on sea in China. It is suggested that NNSA is in charge of the overall safety of a FNPP, while MSA is responsible of the ship survey. The operator shall undertake obligation of a FNPP and evaluate the ship cooperating with experienced agency. It is suggested that government departments build the mutual recognition agreement of safety review. It is better to solve the vague questions by coordination.
4
Fang, Yuan, Xianxing Liu, Xiaoyu Luo, Lei Qiao, Cheng Wang, and Haijun Sun. "Study on the configuration of feed water pump for floating nuclear power plant." In MATERIALS SCIENCE, ENERGY TECHNOLOGY AND POWER ENGINEERING III (MEP 2019). AIP Publishing, 2019. http://dx.doi.org/10.1063/1.5125359.
Full text
5
Ren, Li, Peng Minjun, Xia Genglei, and Zhao Yanan. "Research on Natural Circulation Flow Characteristics of Floating Nuclear Power Plant in Heaving Motion." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66240.
Full textAbstract:
The FNPP (Floating Nuclear Power Plant) expanded the application field of Integrated Pressurized Water Reactor (IPWR) in the movable marine platform, it is necessary to study the natural circulation flow characteristics in heaving motion on the ocean. From the characteristics of FNPP, by means of THEATRe code which was based on the two-phase drift flux model and was modified by adding module calculating the effect of heaving motion, the simulation model in heaving motion was built. Using the models developed, the natural circulation operating characteristics of natural circulation in heaving motion and the transitions between forced circulation and natural circulation are analyzed. In the case of amplitude limited, the periods of mass flow rate are equal to periods of heaving motion. The oscillation amplitude of mass flow rate increases with the heaving amplitude increase. In the case of period limited, the natural circulation flow rate oscillating amplitude increases with the heaving period increases. The result obtained are not only evaluating FNPP design behavior properly but also pointing out the direction to further optimum design to ensure FNPP operating safety in heaving motion.
6
Kindfuller, Vincent, Neil Todreas, Jacopo Buongiorno, Michael Golay, Arthur Birch, Thomas Isdanavich, Ron Thomas, and Harvey Stevens. "Overview of Security Plan for Offshore Floating Nuclear Plant." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-61029.
Full textAbstract:
A new Offshore Floating Nuclear Plant (OFNP) concept with high potential for attractive economics and an unprecedented level of safety is presented, along with an overview of work done in the area of security. The OFNP creatively combines state-of-the-art Light Water Reactors (LWRs) with floating platforms such as those used in offshore oil/gas operations, both of which are well-established technologies which can allow implementation on a time scale consistent with combating climate change in the near future. OFNP is a plant that can be entirely built within a floating platform in a shipyard, transferred to the site. OFNP eliminates earthquakes and tsunamis as accident precursors; its ocean-based passive safety systems eliminate the loss of ultimate heat sink accident by design. The defense of an OFNP poses new security opportunities and challenges compared to land-based plants. Such a plant can be more easily defended by virtue of the clear 360 degree lines of sight and the relative ease of identifying surface threats. Conversely the offshore plant is potentially vulnerable to underwater approaches by mini-submarines and divers. We investigate security considerations of the OFNP applicable to two potential plant options, an OFNP-300 with a 300 MWe reactor, and an OFNP-1100 with an 1100 MWe reactor. Three innovative security system approaches could be combined for the offshore plant. The first is a comprehensive detection system which integrates radar, sonar and unmanned vehicles for a long distance overview of the vicinity of the plant. The second approach is the use of passive physical barriers about 100 meters from the plant, which will force a fast-moving power boat to lose speed or stop at the barrier allowing the plant security force more time to respond. The third approach takes advantage of the offshore plant siting and the monthly or biweekly rotation of crew to reduce the total on-plant and onshore security force by using the off-duty security force on the plant as a reserve force. Through the use of these approaches, the OFNP-300 should be able to achieve a similar security cost (on a per Megawatt basis) as land-based plants of similar or somewhat larger power rating. Due to non-linear scaling of cost, the security cost of the OFNP-1100 has the potential to be reduced significantly compared to its land-based equivalents.
7
Demin, Vladimir F., and Vyacheslav P. Kuznetsov. "Issues of Insurance of Civil Liability for Nuclear Damage From Nuclear Low Power Plants." In ASME 2014 Small Modular Reactors Symposium. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/smr2014-3348.
Full textAbstract:
In the frame of economic analysis of nuclear power (NP) with SMRs in their total life cycle the expert analysis of the problems associated with the civil liability for nuclear damage from SMRs on the example of transportable nuclear power units (TNUs) was performed. Purpose of the analysis is as follows: • Assessment of NP’ safety and economy changes in its development based on TNUs with KLT-40S and partly with RITM-200M reactor units. • Work out of recommendations on this development’ direction in terms of the insurance approach justification and amount of compensation for nuclear damage. The following aspects were considered in the analysis: 1. National and international approaches and practice of nuclear insurance. 2. Specific features of TNUs and differences from large NPPs basing on example of the design of floating power unit FPU “Academician Lomonosov” with KLT-40S reactors. 3. Assessment of severe accident consequences during TNU’ life cycle. 4. Analysis of insurances’ approaches and assessment of possible insurance costs.
8
Cong, Wang, Jue Wang, Hu Chen, Liao Yi, and Chen Lei. "Research on the Passive Residual Heat Removal System of Floating Nuclear Plants." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82219.
Full textAbstract:
For electric energy generation, the design organizations of China have developed variants of floating nuclear plants. Depending on the customer requirement one or more power plants could operating in the same sea area at a time. To achieve a high degree of reactor safety, the passive core cooling subsystems is utilized widely on the floating nuclear plants. This paper conducted a preliminary design of the passive residual heat removal system (PRHRS), which is very important for decay hear removal under the ship blackout accident, used on floating nuclear plants. The limitations due to ocean environment including condition of sea wave and wind, space availability and weight limitations have be considered in the design stage. The computation model of PRHRS was established by use RELAP program. The transient behaviors of PRHRS are simulated. The results showed that PRHRS of floating nuclear plants could achieve the function of remove decay heat and keep reactor core safe under the ship blackout accident with the impact of ocean environment.
9
Yan, Si-wei, Chun-mei Li, Tie-bo Liang, Jing Zhao, Cheng-ming Hao, and Yu Wang. "The Simulation Research of Noncondensable Gas to Condensation in Secondary Side Condenser of Floating Nuclear Power Plant Based on RELAP5." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82222.
Full textAbstract:
Similar to conventional nuclear power plant, condensate water subcooling is a common problem in secondary coolant of floating nuclear power plant, which is caused by many reasons. In this article, RELAP5 is used to simulate the phenomenon of condensate water subcooling caused by noncondensable gas. The influence of noncondensable gas to condenser pressure, subcooling temperature, heat transfer rate, terminal temperature difference, cooling water temperature rise is presented. The results obtained through this study have shown that the model with non-condensable gas in steam can simulate condensate water subcooling, and reveal the discipline of condenser heat transfer characteristics as a function of noncondensable gas content.
10
Takito, Kiyotaka, Osamu Furuya, Hiroshi Kurabayashi, and Kunio Sanpei. "Study on Seismic Isolation and Hi-Frequency Vibration Isolation Technology for Equipment in Nuclear Power Plant Using Aero Floating Technique." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16940.
Full textAbstract:
Abstract In Japan, most structures on the ground surface need seismic countermeasures because of frequently earthquakes. On the other hand, vibration isolation devices are applied to precision or important equipment in several facilities that dislikes vibration in order to reduce daily vibration. In general, vibration isolation devices are intended for high frequency and small amplitude range. However, it is difficult to cut off both vibration region caused by flying object collision and seismic motion with existing technologies. The authors propose insulation of equipment and vibration transmitted through the floor by floating equipment, and have. We have devised and built an air floating device that operates when a trigger input is applied to save the energy of this dynamically acting device. It was estimated by numerical calculation that the aero floating device keeps lifting stably in the condition with the air pressure in the auxiliary air chamber about 75 to 80 kPa. The performance specifications of the proposed device were verified from shaking table test. As a result, the effect of reducing the maximum acceleration by about 1/5 against the seismic motion of El Centro NS, Taft NS, Tohoku NS, and Hachinohe EW was confirmed by floating the mass on the frame assuming the equipment. From the obtained power spectrum diagram (PSD) of the response acceleration, it was confirmed that all frequency components up to 25 Hz is reduced by using proposed aero floating base isolation device.
Reports on the topic "Floating Nuclear Power"
1
Skiba, James M., and Carolynn P. Scherer. Nuclear Security for Floating Nuclear Power Plants. Office of Scientific and Technical Information (OSTI), October 2015. http://dx.doi.org/10.2172/1223744.
Full text