Relevant bibliographies by topics / Quick nuclear reactors

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  1. Journal articles
  2. Dissertations / Theses
  3. Book chapters
  4. Conference papers
  5. Reports

Academic literature on the topic 'Quick nuclear reactors'

Author: Grafiati
Published: 28 May 2022
Last updated: 30 July 2025

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Journal articles on the topic "Quick nuclear reactors"

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Shobeiri, Elaheh, Filippo Genco, Daniel Hoornweg, and Akira Tokuhiro. "Small Modular Reactor Deployment and Obstacles to Be Overcome." Energies 16, no. 8 (2023): 3468. http://dx.doi.org/10.3390/en16083468.

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To meet climate policy goals, it will be necessary to deploy a series of low-carbon energy technologies, including nuclear power. The small modular reactor (SMR) can potentially support climate change mitigation and energy security issues. Small modular reactors (SMRs) are gaining popularity; however, one crucial debate is whether SMRs can compete economically with conventional nuclear reactors or not. From a commercial point of view, SMRs will be able to provide process heat in various industrial applications, replace older nuclear, natural gas, and coal power facilities, and serve smaller en
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Lee, Seung Min, Hana Park, Gwi Sook Jang, and Inkoo Hwang. "Widget-based Alarm Recognition and a Management Support Interface System in Nuclear Power Plants." EPJ Web of Conferences 225 (2020): 03010. http://dx.doi.org/10.1051/epjconf/202022503010.

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As small modular reactors (SMRs) and various computerized operating support systems have been developed, visual display unit(VDU)-based multifunctional consoles have been proposed. The more a console depends on VDUs, the more human system interface (HSI) designers need to consider the decrease in the human performance caused by the effect of navigation tasks. This paper proposes a widget-based alarm recognition and management support interface system to increase the operator’s ability to recognize alarms and to manage alarm-related tasks by reducing additional and excessive navigation tasks. W
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Boschee, Pam. "Comments: Nuclear Energy Gains (Some) Favor." Journal of Petroleum Technology 75, no. 07 (2023): 10–11. http://dx.doi.org/10.2118/0723-0010-jpt.

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Support for nuclear energy in the US is at its highest level in a decade, with 55% of Americans supporting it as a source of electricity. A Gallup poll conducted in March found 25% strongly favor, 30% somewhat favor, while 22% each strongly or somewhat oppose its usage. The report noted that oil prices have generally affected Americans’ responses since the survey was begun in 1994: high oil prices trended with more openness to nuclear energy, low oil prices trended with less favor. As of May, there were 436 nuclear power reactors in operation (connected to the grid) worldwide, providing about
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Zhang, Guo Duo, Xu Hong Yang, Dong Qing Lu, and Yong Xiao Liu. "Research on Pressurizer Pressure Control System Based on BP Neural Network Control of Self-Adjusted PID Parameters." Applied Mechanics and Materials 291-294 (February 2013): 2416–23. http://dx.doi.org/10.4028/www.scientific.net/amm.291-294.2416.

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The pressurizer is an important device in nuclear reactor system, and the traditional PID regulator is usually used to control pressure system of pressurizer in modern reactors. However, it is difficult to get precise parameters of traditional PID controller, and the PID control method is relied on the precise mathematical model badly. And the response of PID controller is often shown by the large amount of overshoot and long setting time which are not the desired results. For such a large inertia and complex time-varying control system, the tradition PID controller can not obtain the satisfy
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Araujo da Silva, Francky Roger, Giovanni Laranjo de Stefani, and Marcelo Vilela da Silva. "Analysis of the SWOT matrix as a strategy for implementing the Ap-Th1000 Reactor in Brazil." Brazilian Journal of Radiation Sciences 12, no. 2 (2024): e2405. http://dx.doi.org/10.15392/2319-0612.2024.2405.

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This article analyzes the SWOT Matrix for the implementation of the AP-Th1000 reactor with thorium fuel, aiming at a future replacement of the current nuclear reactors that use uranium as fuel by thorium. There was a need for an in-depth study of the national and international literature linked to the Brazilian reality. After that, specific meetings were held to detect all possible situations of the 4 main points of the SWOT matrix. During the sessions, which averaged 1 hour, the authors' industrial and academic expertise was demonstrated in competencies such as creativity, collaboration, effe
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Jahangiri, Ali. "Modeling the growth of a vapor film formed in contact between a hot metal sphere and water in pressure vessels." Proceedings of the Institution of Mechanical Engineers, Part E: Journal of Process Mechanical Engineering 233, no. 2 (2018): 184–94. http://dx.doi.org/10.1177/0954408918760894.

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The contact between a hot object such as the particles of a molten metal and a cool and relatively volatile fluid such as water likely takes place in metal casting, paper manufacturing industries, and nuclear reactors. The highly intensive and quick heat transfer caused by the contact may increase the pressure in the vapor film formed on a hot particle within a short period leading to the vapor explosion followed by a strong pressure wave in a vessel containing a volatile matter. The present study aims to provide a mathematical model for contacting between a small hot copper metal sphere and w
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Rodriguez, Gilles, Philippe Amphoux, David Plancq, Edwige Richebois, Frédéric Varaine, and Philippe Bigeon. "The knowledge management on the design of a generation IV sodium fast reactor project at CEA. The case and methodology applied on the Astrid project." EPJ Nuclear Sciences & Technologies 6 (2020): 53. http://dx.doi.org/10.1051/epjn/2020016.

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From 2010 to 2019, the French Alternative Energies and Atomic Commission (CEA) associated with industrial partners realized the Basic Design of a prototype Sodium Fast Reactor. This project was called ASTRID (ASTRID for Advanced Sodium Technological Reactor for Industrial Demonstration). ASTRID design studies were financed through governmental funds until the end of the basic design. These funds covered also the design studies for the core manufacturing workshop, the refurbishment or construction of large test loops. One year before the term of this Basic Design phase (in 2018), industrial par
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Dileep, B. N., P. M. Ravi, Managanvi Sangamesh, and N. Karunakara. "An advanced method for quick detection of heavy water leak in steam generators of pressurized heavy water reactors." Nuclear Engineering and Design 359 (April 2020): 110447. http://dx.doi.org/10.1016/j.nucengdes.2019.110447.

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Rossi, Fabio, Luigi Cosentino, Fabio Longhitano, et al. "The Gamma and Neutron Sensor System for Rapid Dose Rate Mapping in the CLEANDEM Project." Sensors 23, no. 9 (2023): 4210. http://dx.doi.org/10.3390/s23094210.

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The decommissioning of nuclear installations, as well as the possible necessary accident remediations, requires the physical presence of human operators in potentially radiologically hostile environments. The number of active nuclear reactors worldwide is greater than 400, and most of them are 40 to 50 years old, thus implying that soon they will have to be dismantled. In the framework of the H2020 CLEANDEM project, a small robotic vehicle is being developed that is equipped with a series of different sensors for areas that are significantly contaminated by radiation. In this work, we describe
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Nguyen, Son An, Tien Van Dang, Thang Huu Ho, and Hieu Bao Quoc Phan. "Determination of the neutron beam diameter based on the neutron activation analysis." Science and Technology Development Journal 19, no. 4 (2016): 147–53. http://dx.doi.org/10.32508/stdj.v19i4.604.

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Neutron beam diameter is a very important parameter in the experimental nuclear research. Determination of the correct neutron beam diameter is the best method to prepare corectly the optimal sample size correctly, reduced data analysis errors. To measure the neutron diameter, some methods were used: Simulation by Monte – Carlo method, neutron image, and neutron activation analysis. In this report, we determined the neutron beam diameter of the 3rd horizontal channel of the Dalat nuclear reactor that activated gold foils. The result shows that this method offer quick and more correct results t
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Dissertations / Theses on the topic "Quick nuclear reactors"

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Smolikov, A. V., V. I. Pavlenko, V. M. Beresnev, D. A. Kolesnikov, and A. S. Solokcha. "Super Heavy Nano Reinforcing Concrete." Thesis, Sumy State University, 2012. http://essuir.sumdu.edu.ua/handle/123456789/35224.

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The properties of modern heat resistant super heavy concrete reinforced by chrysotile nanotubes are described. When you are citing the document, use the following link http://essuir.sumdu.edu.ua/handle/123456789/35224
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Book chapters on the topic "Quick nuclear reactors"

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Pool, Robert. "Choices." In Beyond Engineering. Oxford University Press, 1997. http://dx.doi.org/10.1093/oso/9780195107722.003.0010.

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During the 1940s and early 1950s, when atomic energy was new, it was common to hear reactors described as nuclear “furnaces.” They “burned” their nuclear fuel and left behind nuclear “ash.” Technically, of course, none of these terms made sense, since burning is a chemical process and a reactor gets its energy from fission, but journalists liked the terminology because it was easy and quick. One loaded fuel into the reactor, flipped a switch, and things got very hot. If that wasn’t exactly a furnace, it was close enough. And actually, the metaphor was pretty good—up to a point. The basement fu
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Fox, Michael H. "Nuclear Waste." In Why We Need Nuclear Power. Oxford University Press, 2014. http://dx.doi.org/10.1093/oso/9780199344574.003.0016.

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I gazed over the railing into the crystal clear cooling pool glowing with blue Cherenkov light caused by particulate radiation traveling faster than the speed of light in water. I can see a matrix of square objects through the water, filling more than half of the pool. It looks like you could take a quick dip into the water, like an indoor swimming pool, but that would not be a good idea! It is amazing to think that this pool, about the size of a ranch house, is holding all of the spent fuel from powering the Wolf Creek nuclear reactor in Burlington, Kansas, for 27 years. The reactor was just
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Shayan Mostafa, Esmaeili, and Ghasemzadeh Farzaneh. "Nuclear Power Plant or Solar Power Plant." In Nuclear Power Plant [Working Title]. IntechOpen, 2020. http://dx.doi.org/10.5772/intechopen.92547.

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Both solar energy and nuclear energy face significant economic challenges. Sustainable energy costs have traditionally been greater than any of those associated with the growth of fossil fuel power generation, although the costs of renewable energy technologies (especially photovoltaic) have dropped. Furthermore, capital costs remain a big challenge in the nuclear generation. In many nations, the cost of building small nuclear power plants is quite large due to time, technology, and environmental and safety challenges for consumers. Such problems might not be as big for state-owned corporation
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Alexandrov, Yu A., and T. F. Drozdova. "Wave Properties of the Neutron and Types of Interaction." In Fundamental Properties of the Neutron. Oxford University PressOxford, 1992. http://dx.doi.org/10.1093/oso/9780198517351.003.0001.

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Abstract The discovery of the neutron in 1932 has undoubtedly had the most profound consequences. With this discovery began the era of nuclear physics in which quick advances gave birth in the middle of this century to nuclear technology and modern particle physics. Since then much has been learned about the neutron. Its interaction with nuclei is rather well studied (the construction of nuclear reactors would be impossible without this). The mass, spin, and magnetic moment of the neutron have been determined, and the knowledge of these, as well as the absence of an electric charge, have made
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Conference papers on the topic "Quick nuclear reactors"

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Lepore, Luigi, Romolo Remetti, and Mauro Cappelli. "Fast Neutron-Flux Monitoring Instrumentation for Lead Fast Reactors: A Preliminary Study on Fission Chamber Performances." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-31011.

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Although Sodium Fast Reactors (SFRs) are the most investigated solutions for the future fast-flux facilities so far, Lead Fast Reactors (LFRs) promise to be a very competitive alternative thanks to their peculiarity concerning coolant-safety, fuel cycle and waste management. Nevertheless, the development of LFRs presents today some drawbacks still to be solved. Due to the harder neutron flux, the current instrumentation developed for SFRs is likely to be extended to LFRs as a first attempt. Otherwise, new monitoring instrumentation could be developed in order to assure more tailored results. D
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Huang, Shanfang, Yaopeng Gong, Chao Li, Ruilong Liu, Jiageng Wang, and Kan Wang. "Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81042.

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Nuclear energy is an important way to solve energy shortage and pollution problems today. Therefore, China is vigorously developing nuclear energy and is facing huge demands for talents. However, nuclear engineering education has been severely hampered, particularly in its experiment aspect because of the Fukushima accident. The original sub-critical nuclear reactor at Tsinghua University (THU) was stopped, forcing students to use computers to conduct relevant nuclear simulation experiments. The emerging of supercomputers and commercial numerical simulation softwares has provided enough hardwa
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Mishra, Rajesh, M. K. Agrawal, K. K. Vaze, and A. K. Ghosh. "Design Strategy for Piping System of an Experimental Facility for Containment Studies." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89040.

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An experimental facility is being set up at Bhabha Atomic Research Centre for studying the thermal-hydraulic behavior of Indian Pressurized Heavy water Reactors under normal and accidental conditions. The set up simulates the containment of the reactor and the Primary Heat Transport System (PHTS). In experimental set up, the PHTS simulation vessel is placed outside the containment building and the piping system connects it to the containment building. The steam-water mixture produced in the PHTS vessel will be discharged into the containment to simulate various postulated accidental conditions
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Upadhyaya, B. R., S. R. P. Perillo, X. Xu, and F. Li. "Advanced Control Design, Optimal Sensor Placement, and Technology Demonstration for Small and Medium Nuclear Power Reactors." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75343.

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The efficient and safe performance of nuclear power plants of the future requires remote monitoring, control, and condition-based maintenance in order to maximize their capacity factor. Small and medium reactors, in the 50–500 MWe power range, may become commonplace for certain applications, with a design features for remote deployment. Such a reactor may be part of a smaller electrical grid, and deployed in areas with limited infrastructure. Typical applications include power generation, process heat for water desalination, and co-generation. There are other considerations in the deployment o
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Povolny, Antonin, Kenichi Katono, Naoyuki Ishida, Kiyoshi Fujimoto, Kenichi Yasuda, and Kazuaki Kito. "Development of Low-Pressure Loss Separator for Advanced BWRs." In 2024 31st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/icone31-133805.

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Abstract In Boiling Water Reactors, steam water mixture is produced by the reactor core. Steam separators separate the steam from the water downstream the core. The steam separators are designed to provide good steam-water separation ratio (limit the carry-over ratio of liquid water in steam and carry-under ratio of steam in water) without inducing too large pressure loss on the recirculation flow (affecting core flow rate or pump power). The steam separators use flow rotation and centrifugal force to separate water from the steam. Good steam-water separation requires stronger rotation within
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Zhu, Wang, Zhang Chunyu, Li Aolin, and Yuan Cenxi. "Three Dimensional Modeling of the Thermo-Mechanical Performance of the Fuel Rods of a PWR." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66010.

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The fuel rods of pressurized water reactors operate under complex radioactive, thermal and mechanical conditions. Multiphysics has to be taken into account in order to evaluate their performance. Many existing fuel rod codes make great simplifications on analyzing the behavior of fuel rods. The present study develops a three dimensional module within the framework of a general-purpose finite element solver, i.e. ABAQUS, for modeling the thermo-mechanical performance of the fuel rods. A typical fuel rod is modeled and the temperature as well as the stress within the pellets are computed. The re
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Qian, Libo, Suizheng Qiu, Dalin Zhang, and Guanghui Su. "Natural Convection With Non-Uniform Heat Generation in Molten Salt Reactor." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75180.

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The Molten Salt Reactor (MSR) is one of the six Generation IV systems capable of breeding and transmutation of actinides and long-lived fission products, which uses the liquid molten salt as the fuel solvent, coolant and heat generation simultaneously. The MSR neutronics, such as the distribution of the delay neutron precursors (DNP), is significantly influenced by the fluid flow, which is quite different from the conventional reactors. Therefore, it is very important to do some research on MSR, especially in accident conditions. The present paper studies the natural convection through which t
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Liu, Jian, Xingchi Jiang, Syed Waqar Ali Shah, et al. "Numerical Model Development for the Transient Heat and Mass Transfer Performance of a Water-Copper Wicked Heat Pipe." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-92297.

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Abstract The application of heat pipes in space nuclear reactors, radiators, and thermal management has gained an enormous amount of attention nowadays. A 3D transient model is needed to study the flow and heat transfer characteristics when considering the complex processes and conditions such as the start-up process, power variation process, non-uniform heating condition, microgravity condition, and so on. In this study, a 3D CFD model for water-copper wicked heat pipe was developed to predict the transient characteristic of heat pipes. A novel source terms method was used through user-define
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Pesetti, Alessio, Mariano Tarantino, and Nicola Forgione. "Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82503.

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The Steam Generator Tube Rupture (SGTR) postulated event constitutes one of the most hazardous safety issues for Gen IV pool reactors, cooled by heavy liquid metals. This accidental scenario is characterized by quick water flashing when in contact with primary coolant liquid metal, causing pressure wave propagation, cover gas pressurization in the reactor main vessel as well as possible tube rupture propagation, vapour dragged through the core, oxides precipitation and consequent slugs and plugs formation. The design phase of Gen IV MYRRHA reactor addressed the SGTR scenario issues in the fram
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Feiye, Liao, Jiang Pingting, Liu Wang, and He Dongyu. "Research on Emergency System of Injection Estimation of Reactor Core Recovery and Reactor Core Decay Heat Removal." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66110.

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One of the lessons learned from Fukushima accident is that the existing procedures used in Nuclear Power Plants (NPPs) are not executed effectively and quickly enough after such an extended accident, for the accident is complex and people are too nervous in such a situation. Thus, emergency system that helps to raise diagnosis efficiency is necessary. In the paper, a quick diagnosis system on injection estimation of reactor core recovery and decay heat removal injection estimation is developed to meet the urgent needs and strengthen requirements for the training and application among utilities
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Reports on the topic "Quick nuclear reactors"

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Gilbert, B. G., R. E. Richards, W. J. Reece, and D. I. Gertman. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR). Version 3.5, Quick Reference Guide. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10185746.

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