Thematische Bibliographien / Safety Shutdown

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Auswahl der wissenschaftlichen Literatur zum Thema „Safety Shutdown“

Autor: Grafiati

Veröffentlicht am 1. Juli 2021

Zuletzt aktualisiert am 4. Februar 2022

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Zeitschriftenartikel zum Thema "Safety Shutdown"

Wilkinson, J. „Emergency Shutdown Safety Systems“. Measurement and Control 20, Nr. 4 (Mai 1987): 49–55. http://dx.doi.org/10.1177/002029408702000403.

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Čepin, Marko. „The extended living probabilistic safety assessment“. Proceedings of the Institution of Mechanical Engineers, Part O: Journal of Risk and Reliability 234, Nr. 1 (31.07.2019): 183–92. http://dx.doi.org/10.1177/1748006x19861199.

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The term living probabilistic safety assessment was defined soon after the initial probabilistic safety assessments were implemented. The objective of this article is to present the extended living probabilistic safety assessment and its applications considering realistic nuclear power plant models, including the low power and shutdown plant operating states. One of the key objectives is to compare the suitability of conventional and additional risk measures, core damage frequency and conditional core damage frequency, respectively. The methods are presented considering all states of the plant from the full power operation to the low power and shutdown states. The example models of the nuclear power plants and the results of the living probabilistic safety assessment of the plant operating states are discussed. The results show that the risk of low power and shutdown states is generally smaller than the risk of full power operation, but the low power and shutdown plant operating states differ significantly among each other regarding the risk level. The deficiency of living probabilistic safety assessment applied to the plant shutdown states is connected with significantly increased human effort for the analyses, with a significantly greater amount of results and with increased uncertainty of some parameters due to the larger dynamics of actions in the plant shutdown versus the full power operation states. The benefit of the living probabilistic safety assessment applied to the plant low power and shutdown states lays in consideration of all states and potential identification of risk significant states and directions for possible safety improvements.

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Čepin, Marko. „Application of shutdown probabilistic safety assessment“. Reliability Engineering & System Safety 178 (Oktober 2018): 147–55. http://dx.doi.org/10.1016/j.ress.2018.05.012.

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Paschal, Lane S., C. L. Bentley, †. Michael E. Dunn, ‡. S. Goluoglu, R. E. Pevey und H. L. Dodds. „Criticality Safety Evaluation of Shutdown Diffusion Cascade Coolers“. Nuclear Technology 119, Nr. 3 (September 1997): 295–305. http://dx.doi.org/10.13182/nt97-a35405.

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Mason, John, und Joe Gluckie. „Modernization of an ammonia plant safety shutdown system“. Process Safety Progress 28, Nr. 3 (September 2009): 282–92. http://dx.doi.org/10.1002/prs.10300.

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Bodizs, L., M. Hahn, A. Rix und J. Schallenberg. „Dynamic models for safety shutdown of distillation columns“. Chemical Engineering Research and Design 99 (Juli 2015): 208–14. http://dx.doi.org/10.1016/j.cherd.2015.03.030.

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Long, An Hou, und Yan Jia Huo. „Buried High Pour-Point Oil Pipeline Shutdown Temperature Drop Research Based on FLUENT“. Applied Mechanics and Materials 444-445 (Oktober 2013): 312–15. http://dx.doi.org/10.4028/www.scientific.net/amm.444-445.312.

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When the buried high pour point oil pipeline is running, it is inevitable to avoid pipeline failures and the pipeline should be shutdown. After shutdown oil temperature dropped and viscosity increased, oil gelling happens, it will cause the accident "condensing tube". For high pour-point oil pipeline can start after shutdown, it should ensure the safety shutdown time of the pipeline and corresponding in the restart pressure. So it is necessary to guide the production practice and pipeline safe operation.

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Liu, Gang, Guo Zhong Zhang und Yuan Yuan Zhang. „Study on the Hot Oil Pipelines’ Cooling Process“. Advanced Materials Research 433-440 (Januar 2012): 4396–400. http://dx.doi.org/10.4028/www.scientific.net/amr.433-440.4396.

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The characteristics of the cooling of waxy crude in pipelines during shutdown depend on the insulation layer thermal resistance and the environment characteristics around the pipe. The crude cooling process in the pipeline is a unsteady heat transfer problem with phase change and a moving phase interface while the wax precipitattion, the properties of the crude depend on the temperature deeply. The cooling process of the hot oil pipeline is simulated. It shows that the computation results are consistent with the test results, based on which analysis has been done, which reveals that many factors affects the cooling. With the shutdown time goes by, high temperature area which lies upper inside the pipe as the result of natural convection after shutdown would move adown gradually to the lower part inside pipe. And the bigger the pipe is, the longer the safety shutdown is; the higher original temperature also contributes to the safety restart.

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Skvortsov, M. S. „Design Assessment of Functional Safety of Emergency Shutdown System“. Occupational Safety in Industry, Nr. 1 (Januar 2018): 50–57. http://dx.doi.org/10.24000/0409-2961-2018-1-50-57.

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Boustani, Ehsan, Samad Khakshournia und Hossein Khalafi. „A pragmatic approach towards designing a second shutdown system for Tehran research reactor“. Nuclear Technology and Radiation Protection 31, Nr. 1 (2016): 28–36. http://dx.doi.org/10.2298/ntrp1601028b.

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One second shutdown system is proposed for the Tehran Research Reactor to achieve the goal of higher safety in compliance with current operational requirements and regulations and improve the overall reliability of the reactor shutdown system. The proposed second shutdown system is a diverse, independent shutdown system compared to the existing rod based one that intends to achieve and maintain sub-criticality condition with an enough shutdown margin in many of abnormal situations. It is designed as much as practical based on neutron absorber solution injection into the existing core while the changes and interferences with the existing core structure are kept to a minimum. Core neutronic calculations were performed using MCNPX 2.6.0 and MTR_PC package for the current operational core equipped with the second shutdown system, and one experiment was conducted in the Tehran Research Reactor to test the neutronic calculations. A good agreement was seen between theoretical results and experimental ones. In addition, capability of the second shutdown system in the case of occurrence of design basis accident in the Tehran Research Reactor is demonstrated using PARET program.

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Dissertationen zum Thema "Safety Shutdown"

Vo, Do. „Automation, Annunciation, and Emergency Safety Shutdown of a Laboratory Microgrid Using a Real-Time Automation Controller (RTAC)“. DigitalCommons@CalPoly, 2021. https://digitalcommons.calpoly.edu/theses/2292.

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Over the last decade, microgrid deployments throughout the world have increased. In 2019, a record number of 546 microgrids were installed in the United States [1]. This trend continues upward to combat extreme weather conditions and power shortages throughout the country. To better equip students with the necessary skillsets and knowledge to advance in the microgrid field, Cal Poly San Luis Obispo's Electrical Engineering Department and the Power Energy Institute have invested resources to develop a laboratory microgrid. This thesis sets to improve the laboratory microgrid's existing automation using the Schweitzer Engineering Laboratory SEL-3530 Real-time Automation Controller (RTAC). The improved automation features a new load-shedding scheme, LCD annunciator and meter panel, and emergency safety shutdown system. The load shedding scheme aims to enhance the grid's frequency stability when the inverter-based power output declines. The LCD annunciator and meter panels provide real-time oversight of the microgrid operating conditions via the RTAC Human Machine Interface (HMI). The emergency safety shutdown enables prompt de-energization and complete isolation of the laboratory microgrid in hazardous conditions such as earthquake, fire, arcing, and equipment malfunction and activates an audible siren to alert help. This safety system provides safety and peace of mind for students and faculties who operate the Microgrid. Lastly, this thesis provides an operating procedure for ease of operation and experiment.

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VIVAS, ARY de S. „Desenvolvimento do plano preliminar de descomissionamento do reator IPEN/MB-01“. reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/23487.

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Submitted by Maria Eneide de Souza Araujo (mearaujo@ipen.br) on 2015-02-20T15:58:48Z No. of bitstreams: 0
Made available in DSpace on 2015-02-20T15:58:48Z (GMT). No. of bitstreams: 0
Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP

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Wang, Yi. „SBLOCA analysis for nuclear plant shutdown operations“. Thesis, 1994. http://hdl.handle.net/1957/35895.

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A series of small break loss of coolant accident (SBLOCA) analyses in nuclear plant shutdown operations was simulated using the code RELAP5A,MOD3 version 8.0 to predict the SBLOCA phenomena in the Zion-l nuclear power plant The first objective is to study the impact of SBLOCA (1" and 2" breaks) on plant conditions while in the shutdown mode. In particular, to determine the time to "core uncovery" without operator interaction. The other objective is to study the effect of RHR heat exchanger elevation on natural circulation mass flow rate, fluid temperature and peak fuel pin temperature. Peak temperature and time to core uncovery were found for two small break LOCA cases. The natural circulation mass flow rate after break initiation was affected by varying the RHR heat exchanger elevation. The system pressure and temperature were not affected much by the elevation change in the RHR heat exchanger. The current version of RELAP5/MOD3 was found to be sensitive to the initial conditions in studies of low pressure,low temperature plant systems, especially for a large break LOCA.
Graduation date: 1994

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Lin, Chin-Cheng, und 林晉成. „The Safety Analysis of core spent-fuel under Chinshan Nuclear Power Plant cold shutdown operational mode“. Thesis, 2018. http://ndltd.ncl.edu.tw/handle/7b2qu4.

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CHIN, FONG-LI, und 金峯立. „Application of Knowledge Management and TRIZ improve the Post-fire Safe Shutdown Capability for the nuclear power plant“. Thesis, 2013. http://ndltd.ncl.edu.tw/handle/60777012949404148631.

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碩士
國立高雄應用科技大學
工業工程與管理系碩士班
101
The safety of nuclear power generation became the focus of the world especially after the Fukushima nuclear disaster after the 2011 Tohoku earthquake. There are a lot of elements that needs to be considered in the early stages of designs of Nuclear Power Plants. With the consideration of such elements in the early stages of design it can secure the power plant in safety shutdowns. Therefore the US Nuclear Regulatory Commission has formulated various fire regulations, The safe shutdown capability of nuclear power plants have reached a basic ability to ensure that one of the fire will not affect the safety shutdown system failure. This study uses the Problem Hierarchy Analysis to clearly define the required elements in focus. Using the Knowledge Management ways build a Post-Fire Safe Shutdown Capability database. Using the TRIZ method solved according NRC standards in a safe shutdown procedure not matched. An Asia nuclear power plant case study will be provided the Post Fire Safe Shutdown capability using the TRIZ method systemic innovation combined with Knowledge Management practices effectively sophisticated of safe shutdown capability database, and indeed make 22 cables that does not match the regulatory requirements from the 850000 paths reduced to 0. This also verifies reaching the demand for nuclear energy regulations in order to enhance the safety of nuclear power plant and future industry requirements in a systemic innovative way for reference.

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Bücher zum Thema "Safety Shutdown"

Harry, Cheddie, Hrsg. Safety shutdown systems: Design, analysis, and justification. Research Triangle Park, NC: Instrument Society of America, 1998.

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Practical industrial safety, risk assessment and shutdown systems for industry. Oxford: Newnes, 2004.

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Office, General Accounting. Nuclear regulation: NRC needs to more aggressively and comprehensively resolve issues related to the Davis-Besse nuclear power plant's shutdown : report to Congressional Requesters. [Washington, D.C.]: GAO (441 G St. NW, Room LM, Washington D.C., 20548), 2004.

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Gordon, Joshua. Sleeping on the job: Shutdown of Peach Bottom Nuclear Power Plant highlights lax federal oversight of nuclear safety : government documents reveal that nuclear reactor operators regularly fall asleep on the job. Washington, D.C: Public Citizen, Critical Mass Energy Project, 1987.

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Practical Industrial Safety, Risk Assessment and Shutdown Systems. Elsevier, 2003. http://dx.doi.org/10.1016/b978-0-7506-5804-1.x5000-9.

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Wang, I. SBLOCA analysis for nuclear plant shutdown operations. 1994.

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Safety Considerations for Research Reactors in Extended Shutdown (Iaea Tecoc Series). International Atomic Energy Agency, 2004.

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Sahoo, Trinath. Process Plants: Shutdown and Turnaround Management. Taylor & Francis Group, 2017.

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Process Plants: Shutdown and Turnaround Management. Taylor & Francis Group, 2013.

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Agency, International Atomic Energy, Hrsg. Safety analysis of nuclear power plants during low power and shutdown conditions. Vienna, Austria: International Atomic Energy Agency, 1998.

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Buchteile zum Thema "Safety Shutdown"

Čepin, Marko, und Mitja Antonči. „Shutdown probabilistic safety assessment—method and results“. In Risk, Reliability and Safety: Innovating Theory and Practice, 723–27. Taylor & Francis Group, 6000 Broken Sound Parkway NW, Suite 300, Boca Raton, FL 33487-2742: CRC Press, 2016. http://dx.doi.org/10.1201/9781315374987-109.

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Kovacs, Zoltan. „Level 1 Low Power and Shutdown PSA“. In Probabilistic Safety Assessment of WWER440 Reactors, 211–48. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-08548-7_4.

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Tripathi, Manish, Sonali Parmar, C. Bose, Vibha Hari, A. K. Vijaya, N. Mohan und Mukesh Singhal. „Shutdown Probabilistic Safety Assessment of Boiling Water Reactor“. In Reliability, Safety and Hazard Assessment for Risk-Based Technologies, 59–70. Singapore: Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-9008-1_6.

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Sakuramoto, Kazuo, Koichi Miyata und Shigeatsu Tomizawa. „Evaluation of Shutdown Risk Using FT-FREE Risk Monitoring Function“. In Probabilistic Safety Assessment and Management, 3170–76. London: Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_508.

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Tae-Yong, Sung, Park Jin Hee und Kim Tae-Woon. „Role of PSA in Improving Plant Safety During Shutdown Operation“. In Probabilistic Safety Assessment and Management ’96, 46–51. London: Springer London, 1996. http://dx.doi.org/10.1007/978-1-4471-3409-1_8.

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Holý, Jaroslav. „Some Insights from HRA Related to Low Power and Shutdown Scenarios“. In Probabilistic Safety Assessment and Management, 1741–47. London: Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_279.

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Thompson, C. J. „Safety Issues Associated with Safe Shutdown and Operation of Plutonium Processing Plants“. In Nuclear Materials Safety Management Volume II, 165–73. Dordrecht: Springer Netherlands, 1999. http://dx.doi.org/10.1007/978-94-011-4501-5_22.

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Revenko, Yu A., Yu P. Sorokin und N. N. Sergeyev. „Safety Problems Related to the Operation and Shutdown of Radiochemical Production“. In Nuclear Materials Safety Management Volume II, 149–56. Dordrecht: Springer Netherlands, 1999. http://dx.doi.org/10.1007/978-94-011-4501-5_20.

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Kovacs, Zoltan, und Ignac Pnacek. „Level 2 Full Power and Shutdown PSA of the J. Bohunice VI NPP“. In Probabilistic Safety Assessment and Management, 278–83. London: Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_45.

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Berg, Heinz Peter, Marina Röwekamp, Michael Türschmann und Joachim von Linden. „First Experiences Regarding Probabilistic Fire Safety Assessment for Full Power and Low Power/Shutdown Operational States“. In Probabilistic Safety Assessment and Management, 2468–73. London: Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_396.

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Konferenzberichte zum Thema "Safety Shutdown"

Torres, Raymund J., und Brian C. Boggan. „From planned to unplanned shutdown“. In 2017 IEEE IAS Electrical Safety Workshop (ESW). IEEE, 2017. http://dx.doi.org/10.1109/esw.2017.7914835.

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Heraiba, F. A., und O. A. Rahman. „Safety and Shutdown Systems for Offshore Facilities“. In Middle East Oil Show. Society of Petroleum Engineers, 1993. http://dx.doi.org/10.2118/24519-ms.

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Cepin, Marko. „House events matrix for shutdown probabilistic safety assessment“. In 2016 International Conference on Probabilistic Methods Applied to Power Systems (PMAPS). IEEE, 2016. http://dx.doi.org/10.1109/pmaps.2016.7764191.

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Cordova, Adam, Christopher Merz, Gerd Bettenwort, Markus Hopf, Hannes Knopf und Joachim Laschinski. „Rapid Shutdown with Panel Level Electronics-A suitable safety measure?“ In 2017 IEEE 44th Photovoltaic Specialists Conference (PVSC). IEEE, 2017. http://dx.doi.org/10.1109/pvsc.2017.8366726.

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Li, Lin, und Bo Zhao. „Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions“. In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29007.

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For nuclear power plant, probabilistic safety assessment (PSA) is an effective tool for risk evaluating, risk recognizing and risk managing. This paper initiate a study focused on shutdown safety for NPP as well as the related PSA approaches. Especially, a PSA preliminary analysis and estimation on shutdown operation to the 1000 MWe NPP are performed. The first part of this thesis presents the methods used in the classification of plant operation state (POS), the identification of initiating event and the quantification of initiating event frequency. The second part centers on configuration of shutdown model used in PSA. Based on the design and operation features during shutdown conditions of NPPs, event trees for the shutdown model are constructed and Human Reliability Analysis (HRA) is performed. The last part is the quantification of the integrated shutdown model by means of Risk Spectrum software. System analysis is based on FuQing nuclear power plant PSA report. Component failure data and initiating event frequencies are largely based on EPS900 or NUREG./CR-6144. Overall point estimation of core damage frequency (CDF) during shutdown is assessed; the most important risk contributors of plant operational states, the dominant initiating events and their contribution to CDF are described respectively.

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Watanabe, Takeshi, Hidenori Tanaka, Makoto Arinaga und Yasunori Fuchikami. „Safety shutdown of process equipment by automatic remote operation — Kuniaki Ishimoto“. In 2017 Joint International Symposium on e-Manufacturing and Design Collaboration (eMDC) & Semiconductor Manufacturing (ISSM). IEEE, 2017. http://dx.doi.org/10.23919/issm.2017.8089105.

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Goyal, Ram. „Impact Of Emergency Shutdown Devices On Relief System Sizing And Design“. In SPE Middle East Health, Safety, Environment & Sustainable Development Conference and Exhibition. Society of Petroleum Engineers, 2014. http://dx.doi.org/10.2118/170346-ms.

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Sigmundstad, Jone Nicolai, und Ellen Lycke. „Novel Application of Technology in Subsea Safety Instrumented System: Battery-Based Shutdown System“. In Proceedings of the 31st European Safety and Reliability Conference. Singapore: Research Publishing Services, 2021. http://dx.doi.org/10.3850/978-981-18-2016-8_073-cd.

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Hsu, Hao-Ti, Ching-Han Chen, Ching-Tien Huang und Chung-Kung Lo. „The Risk Effectiveness of Installing RCP Shutdown Seal for Loss of CCW Event“. In Proceedings of the 29th European Safety and Reliability Conference (ESREL). Singapore: Research Publishing Services, 2019. http://dx.doi.org/10.3850/978-981-11-2724-3_0996-cd.

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Vijayashree, R., P. ChellaPandi, K. Natesan, S. Jalaldeen, S. C. Chetal und Baldev Raj. „Design and Development of Diverse Safety Rod and Its Drive Mechanism for PFBR“. In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75851.

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Prototype Fast Breeder Reactor (PFBR) is U-PuO2 fuelled sodium cooled Pool type Fast Reactor and it is currently under advanced stage of construction at Kalpakkam, India. The Fast Breeder Test Reactor (FBTR) which is the only fast reactor currently operational in India is having only one shutdown system. However the IAEA and Atomic Energy Regulatory Board (AERB) Guide Lines call for two independent fast acting diverse shutdown systems for the present generation reactors. Hence PFBR is equipped with two independent, fast acting and diverse shutdown systems. A shutdown system comprises of sensors, logic circuits, drive mechanisms and neutron absorbing rods. The two shutdown systems of PFBR are capable of bringing down the reactor to cold shutdown state independent of the other. The absorber rods of the second shutdown system of PFBR are called as Diverse Safety rods (DSR) and their drive mechanisms are called as Diverse Safety Rod Drive Mechanisms (DSRDM). DSR are normally parked above active core by DSRDM. On receiving scram signal, Electromagnet of DSRDM is de-energised and it facilitates fast shutdown of the reactor by dropping the DSR in to the active core. This paper presents chronological design and development of the prototype DSR and DSRDM starting from the design specifications. Salient design specifications for both DSRDM and DSR are listed initially. The conceptual & detailed design features are explained with the help of figures. Various important design options considered in the initial design stage, choice of final design along with brief explanation for the particular choice are also given for some of the important components. Details on material of construction are given at appropriate places. Details on various analysis such as large displacement analysis for buckling, bending analysis for determining reactive forces and friction in the mechanism, thermal stress analysis of electromagnet during scram, flow induced vibration analysis of DSRDM and DSR and hydraulic analysis for estimating the pressure drop and drop time of DSR are also given. Test plans for design verification, manufacturing and shop testing experience of prototype systems, and criteria for endurance testing in sodium for qualification of DSRDM and DSR for operation in reactor are also briefed.

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Berichte der Organisationen zum Thema "Safety Shutdown"

BENECKE, M. W. Fuel Supply Shutdown Facility Technical Safety Requirements. Office of Scientific and Technical Information (OSTI), Februar 2003. http://dx.doi.org/10.2172/810504.

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Besser, R. L., J. R. Brehm, M. W. Benecke und J. A. Remaize. Fuel supply shutdown facility interim operational safety requirements. Office of Scientific and Technical Information (OSTI), Mai 1995. http://dx.doi.org/10.2172/67268.

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BENECKE, M. W. Interim Safety Basis for Fuel Supply Shutdown Facility. Office of Scientific and Technical Information (OSTI), September 2000. http://dx.doi.org/10.2172/804807.

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BENECKE, M. W. Fuel Supply Shutdown Facility Interim Operational Safety Requirements. Office of Scientific and Technical Information (OSTI), September 2000. http://dx.doi.org/10.2172/804808.

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Brehm, J. R., T. L. Deobald, M. W. Benecke und J. A. Remaize. Interim safety basis for fuel supply shutdown facility. Office of Scientific and Technical Information (OSTI), Mai 1995. http://dx.doi.org/10.2172/80372.

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Zuroff, W. F. Acceptance test report for the safety class shutdown system. Office of Scientific and Technical Information (OSTI), Oktober 1996. http://dx.doi.org/10.2172/332189.

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Travis, R. J., R. E. Davis, E. J. Grove und M. A. Azarm. A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants. Office of Scientific and Technical Information (OSTI), August 1997. http://dx.doi.org/10.2172/510336.

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Keck, R. D. Definition and means of maintaining the supply ventilation system seismic shutdown portion of the PFP safety envelope. Office of Scientific and Technical Information (OSTI), Januar 1997. http://dx.doi.org/10.2172/325844.

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Keck, R. D. Definition and means of maintaining the supply ventilation system seismic shutdown portion of the PFP safety envelope. Revision 2. Office of Scientific and Technical Information (OSTI), Juni 1995. http://dx.doi.org/10.2172/88529.

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Muna, Alice, und Chris LaFleur. Post-Fire Safe Shutdown Capability. Office of Scientific and Technical Information (OSTI), Februar 2017. http://dx.doi.org/10.2172/1762036.

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