Relevant bibliographies by topics / Environmental aspects of Nuclear reactor accidents

Contents

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

Academic literature on the topic 'Environmental aspects of Nuclear reactor accidents'

Author: Grafiati
Published: 4 June 2021
Last updated: 10 February 2022

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Journal articles on the topic "Environmental aspects of Nuclear reactor accidents"

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Leishear, Robert A. "From Water Hammer to Ignition." Mechanical Engineering 136, no. 12 (2014): 44–47. http://dx.doi.org/10.1115/1.2014-dec-3.

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This article focuses on various aspects of research theory and development work concerning accidental combustion in nuclear facility and oil industry pipelines. The theory has safety implications for any pipeline where explosive gases can form in liquid-filled systems, and is consistent with pipeline accidents in nuclear power plants, such as Three Mile Island. Nuclear reactor accidents deserve further investigation, since reactor fires and explosions were ignited by sources that were reported to be unknown. The NRC documented extensive actions to improve reactor safety after the Three Mile Is
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Fulker, M. J. "Aspects of environmental monitoring by British nuclear fuels plc following the chernobyl reactor accident." Journal of Environmental Radioactivity 5, no. 3 (1987): 235–44. http://dx.doi.org/10.1016/0265-931x(87)90038-5.

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Karlsson, Erik, Jörg Neuhausen, Robert Eichler, Ivan I. Danilov, Alexander Vögele, and Andreas Türler. "Thermochromatographic behavior of iodine in 316L stainless steel columns when evaporated from lead–bismuth eutectic." Journal of Radioanalytical and Nuclear Chemistry 328, no. 2 (2021): 691–99. http://dx.doi.org/10.1007/s10967-021-07682-3.

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AbstractIodine evaporated from lead–bismuth eutectic (LBE) has been examined with respect to its adsorption behavior on stainless steel in various gases to establish a base for safety evaluations on LBE based nuclear reactors. In inert conditions the iodine forms a single species with an adsorption enthalpy between − 97 and − 106 kJ/mol. The adsorbed species is tentatively identified as bismuth monoiodide, BiI. Addition of moisture to the inert gas has no substantial influence on the adsorption behaviour. For the reducing hydrogen carrier gas depositions with adsorption enthalpies ranging from
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Qiu-kuan, Wang, Lin Chang-hua, and Yang Yan. "Advanced Measuring (Instrumentation) Methods for Nuclear Installations: A Review." Science and Technology of Nuclear Installations 2012 (2012): 1–9. http://dx.doi.org/10.1155/2012/672876.

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The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation) methods for nuclear installations and the applications of these instruments and methods.
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Flores y Flores, Alain, Danilo Ferretto, Tereza Marková, and Guido Mazzini. "Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2." Sustainability 13, no. 14 (2021): 7964. http://dx.doi.org/10.3390/su13147964.

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The severe accident integral codes such as Methods for Estimation of Leakages and Consequences of Releases (MELCOR) are complex tools used to simulate and analyse the progression of a severe accident from the onset of the accident up to the release from the containment. For this reason, these tools are developed in order to simulate different phenomena coupling models which can simulate simultaneously the ThermoHydraulic (TH), the physics and the chemistry. In order to evaluate the performance in the prediction of those complicated phenomena, several experimental facilities were built in Europ
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Corradini, M. L. "Current aspects of LWR containment loads due to severe reactor accidents." Nuclear Engineering and Design 122, no. 1-3 (1990): 287–99. http://dx.doi.org/10.1016/0029-5493(90)90213-h.

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Engler, John-Oliver. "Global and regional probabilities of major nuclear reactor accidents." Journal of Environmental Management 269 (September 2020): 110780. http://dx.doi.org/10.1016/j.jenvman.2020.110780.

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Sharaievskii, I., N. Fialko, A. Nosovsky, L. Zimin, and G. Sharaievskii. "Urgent Problems in Thermal Physics of Design-Basis and Severe Accidents at Nuclear Power Plants." Nuclear and Radiation Safety, no. 2(70) (May 20, 2016): 32–36. http://dx.doi.org/10.32918/nrs.2016.2(70).07.

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The paper considers thermal and physical aspects in dynamics of design-basis and severe accidents at water-cooled nuclear power reactors with nuclear fuel damage. The most promising concepts of the corium confinement in the damaged reactor were analyzed. The main objective was to define the main areas to search and implement methods of efficient and safe heat removal in progression of emergencies.
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Komarov, Alexander, and Nikolay Gromov. "Particular aspects of calculating affecting factors of fireballs emerging from aircraft crash." MATEC Web of Conferences 251 (2018): 02031. http://dx.doi.org/10.1051/matecconf/201825102031.

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The article reveals an algorithm of calculating the heat loads which emerge during fireball-involving accidents. By way of illustration it considers a situation when a heavy aircraft crashes in the vicinity of a typical reactor building of a nuclear power plant. The given algorithm provides a quite detailed and accurate calculation of maximum heat load values that accompany the accident.
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Beard, A. M., P. J. Bennett, B. R. Bowsher, and J. Brunning. "The falcon programme: characterisation of multicomponent aerosols in severe nuclear reactor accidents." Journal of Aerosol Science 23 (January 1992): 831–34. http://dx.doi.org/10.1016/0021-8502(92)90540-c.

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Dissertations / Theses on the topic "Environmental aspects of Nuclear reactor accidents"

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Zarimpas, N. "Modelling in-plant aspects of nuclear reactor accidents." Thesis, Imperial College London, 1985. http://hdl.handle.net/10044/1/37909.

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Missfeldt, Fanny. "Strategic aspects of nuclear safety in Eastern and Western Europe." Thesis, University of Stirling, 1998. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.297778.

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Cheng, Kit-yan Ruby, and 鄭潔茵. "Nuclear emergency preparedness model based on Daya Bay Nuclear Power stations for educational purposes." Thesis, The University of Hong Kong (Pokfulam, Hong Kong), 2005. http://hub.hku.hk/bib/B36168464.

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Books on the topic "Environmental aspects of Nuclear reactor accidents"

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Gordon, Joshua. Consequences of a nuclear accident. Public Citizen, Critical Mass Energy Project, 1989.

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Radioactive fallout after nuclear explosions and accidents. Elsevier, 2002.

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Jensen, Per Hedemann. Atmospheric dispersion and environmental consequences. Risø NationalLaboratory, 1992.

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Jensen, Per Hedemann. Intervention levels for protective measures in nuclear accidents: International intervention policy and Nordic status on intervention. Risø National Laboratory, 1992.

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Jensen, Per Hedemann. Atmospheric dispersion and environmental consequences: Exposure from radioactive plume pathways. Risø National Laboratory, 1992.

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Bailey, C. C. The aftermath of Chernobyl: History's worst nuclear power reactor accident. Kendall/Hunt Publishing Co., 1989.

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steadman, Philip. Nuclear disasters & the built environment: A report to the Royal Institute of British Architects. Butterworth Architecture, 1990.

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Molitor, Marc. Tchernobyl: Déni passé, menace future? Racine, 2011.

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International Symposium "Sarcophagus Safety '94" (1994 Zelenyĭ Mys, Chornobylʹ, Ukraine). "Sarcophagus Safety '94": The state of the Chernobyl Nuclear Power Plant Unit 4 : proceedings of an International Symposium, Zeleny Mys, Chernobyl, Ukraine, 14-18 March 1994. Nuclear Energy Agency, Organisation for Economic Co-Operation and Development, 1995.

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I︠A︡blokov, A. V. Chernobyl: Consequences of the catastrophe for people and the environment. Edited by Nesterenko Vasiliĭ Borisovich, Nesterenko Alexey V, and Sherman Janette D. Published by Blackwell Pub. on behalf of the New York Academy of Sciences, 2009.

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Book chapters on the topic "Environmental aspects of Nuclear reactor accidents"

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Casini, G. "Feasibility Aspects of the D-3He Fuel Cycle in Tokamak Power Reactor Plants." In Safety, Environmental Impact, and Economic Prospects of Nuclear Fusion. Springer US, 1990. http://dx.doi.org/10.1007/978-1-4613-0619-1_10.

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Theophilopoulos, Nick A., and Pavlos Kassomenos. "Modelling and Simulation of Environmental Hazards." In Environmental Information Systems in Industry and Public Administration. IGI Global, 2001. http://dx.doi.org/10.4018/978-1-930708-02-0.ch017.

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Emergencies are most probably the most important issue at the European and, of course, at the international level, in terms of impact to the economic structures, the ecosystems,and human and environmental resources. A number of emergencies have been identified within the Emergency Management Area and the areas under EMA coverage. These could be summarised as forest fires, chemical fires, structural fires, industrial accidents, oil and chemical spills, explosions, nuclear accidents, radiation, storms, tornadoes, floods, dam ruptures, marine algal blooms, avalanches, landslides, earthquakes, seismic waves, and volcanic eruptions. The modelling and simulation of the environmental hazards in Europe should be harmonised in a way where developments will proceed, through a consensus mechanism, between the industry, the users, and the standardisation organisations, to create a consensus approach by identifying best practice cases in the management (including detection surveillance and monitoring of the emergency), and to plan operational aspects of the emergency situations, identify proper technological breakthroughs, and identify techniques and developments.
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Conference papers on the topic "Environmental aspects of Nuclear reactor accidents"

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Yan, Shiyu, Hua Liu, Zhaohui Liu, Xiaohua Yang, Meng Li, and Zhi Chen. "A New Safety Analysis Method of Control Rod Ejection Accident in PWR NPP Based on the Failure of Causal Relationship." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81879.

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In view of control rod ejection accident of the traditional pressurized water reactor, the safety thought of the design phase is to validate reliability and availability of DCS I&C in the severe accidents. Now the most important and effective means is simulation calculation and analysis. It is applied for the imaginary accident of the nuclear power plant by using computer software. The new safety analysis steps based on the analysis of cause-and-effect logic failure: firstly, the composition and working principle of control rod drive mechanism is analyzed; secondly, a list of factors-the d
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Li, Jingxi, Gaofeng Huang, and Lili Tong. "Evaluation on Radiological Consequence Induced by MSLB Accident With Alternative Source Term." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29615.

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The major threat that nuclear power plants (NPPs) pose to the safety of the public comes from the large amount radioactive material released during design-basis accidents (DBAs). Additionally, many aspects of Control Room Habitability, Environmental Reports, Facility Siting and Operation derive from the design analyses that incorporated the earlier accident source term and radiological consequence of NPPs. Depending on current applications, majority of Chinese NPPs adopt the method of TID-14844, which uses the whole body and thyroid dose criteria. However, alternative Source Term (AST) are com
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Awan, Muhammad Qasim, Liangzhi Cao, and Hongchun Wu. "Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66444.

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The Fukushima Daiichi Nuclear Power Plant accident in Japan was one of the severest accidents in history of nuclear power plants. This accident changed the prospect of the Nuclear Engineers all around the globe, regarding safety enhancement of nuclear reactors. Since then many aspects of nuclear reactors regarding the improvements of safety features are under investigation and R&D efforts are underway around the world. Use of innovative fuels in present as well as future reactor designs is one of the major potential areas of these ongoing efforts. Fully Ceramic Micro-Encapsulated (FCM) fue
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Ting, Yang, Li Guang Sheng, Li Zeng Fen, Peng Yue, and Hu Jian. "Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66189.

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For nuclear power stations, the main function of Essential Service Water System (ESWS) is to discharge the waste heat from reactor core and spent fuel pool to the environment controllably, which is directly related to the safety and economy of nuclear power stations. Usually ESWS use open water from sea, rivers, lakes, reservoirs, as heat transfer medium. Extremely harsh environmental conditions may disable system functions and even lead to ESWS failure, directly reduce the safety and economy of nuclear power stations, and cause serious nuclear accidents. Failure of ESWS is one of the main rea
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Farrell, Ronald S. "Some Practical Aspects of Class 1E Actuator Qualification on Comparing Test Levels and Design Basis Event Loading." In ASME 2016 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/pvp2016-63526.

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All power operated valve actuators that perform a critical safety function in nuclear power plants must be backed by testing to demonstrate they are capable of reliably performing their safety related function. Such actuators are denoted Class 1E and must be qualified according to IEEE-382 “Standard for Qualification of Actuators for Power-Operated Valve Assemblies with Safety-Related Functions for Nuclear Power Plants” which states that a Class 1E Actuator is essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, or othe
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Kirillov, P. L. "SOME ASPECTS OF HEAT TRANSFER DURING NUCLEAR REACTOR ACCIDENTS." In International Heat Transfer Conference 10. Begellhouse, 1994. http://dx.doi.org/10.1615/ihtc10.1950.

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Sahoo, Pradeep K., and Ankit Singh. "Development of Experimental Facility to Study Channel Disassembly Behaviour for Indian PHW Reactor During Heatup." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81312.

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No experimental investigation has been carried out to understand the progression of channel disassembly in IPHWR. Hence, it is planned to study the deformations aspects through experiments with a scaled-down (1:3) fuel channel of 220MWe reactor. Depending upon the pressure inside the channel and transient past, the accident initiation and disassembly can be can be classified into two class. In the first case, high pressure inside channel leads PT ballooned and fully contacted CT before channel deformed as one composite unit. While in second case, low inside pressure, first leads PT to contact
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Balz, W., B. R. Bowsher, C. G. Benson, and E. Delia Loggia. "CEC REINFORCED CONCERTED ACTION ON REACTOR SAFETY: PRIMARY CIRCUIT ASPECTS OF THE SOURCE TERM PROJECT." In Heat and Mass Transfer in Severe Nuclear Reactor Accidents. Proceedings of the International Symposium. Begellhouse, 1995. http://dx.doi.org/10.1615/ichmt.1995.radtransfprocheatmasstransfsevnuclreactacc.140.

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Wallner, Christian, Anna-Maria Rall, and Severin Thummerer. "Using Probabilistic Criteria in an Assessment of the Potential Radiological Consequences of the Decommissioning of a Nuclear Research Reactor." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96085.

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In order to assess the risk of radiological consequences of incidents and accidents in nuclear facilities it is important to contemplate their frequency of occurrence. It has to be shown that incidents and accidents occur sufficiently seldom according to their radiological consequences i. e. the occurrence frequency of radiological doses has to be limited. This is even demanded by the German radiation protection ordinance (StrlSchV), which says that in nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, the occurrence frequency of incidents and accide
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Xu, Jim. "Overview of Implementation of Probabilistic-Risk-Assessment-Based Seismic Margin Analyses in Design Certification and Combined License Applications." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25160.

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The licensing process for new reactors in the United States was established in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” which provides requirements for early site permit (ESP), standard design certification (DC), and combined license (COL) applications. In this process, an application for a COL may incorporate by reference a DC, an ESP, both, or neither. This approach allows for the early resolution of safety and environmental issues. The safety issues resolved by the DC and ESP processes a
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