Zeitschriftenartikel: „Safety Shutdown“

1

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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2

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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3

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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4

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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5

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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6

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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7

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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8

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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9

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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10

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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Costa, M. „Safety classification of the ITER fusion power shutdown system and resulting safety requirements“. Fusion Engineering and Design 54, Nr. 3-4 (April 2001): 361–74. http://dx.doi.org/10.1016/s0920-3796(00)00555-x.

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12

Touahar, Hafed, Nouara Ouazraoui, Nor El Houda Khanfri, Mourad Korichi, Bilal Bachi und Houcem Eddine Boukrouma. „Multi-objective optimization of safety instrumented systems maintenance strategy: a case study“. International Journal of Quality & Reliability Management 38, Nr. 8 (25.01.2021): 1792–815. http://dx.doi.org/10.1108/ijqrm-03-2020-0076.

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PurposeThe main objective of safety instrumented systems (SISs) is to maintain a safe condition of a facility if hazardous events occur. However, in some cases, SIS's can be activated prematurely, these activations are characterized in terms of frequency by a Spurious Trip Rate (STR) and their occurrence leads to significant technical, economic and even environmental losses. This work aims to propose an approach to optimize the performances of the SIS by a multi-objective genetic algorithm. The optimization of SIS performances is performed using the multi-objective genetic algorithm by minimizing their probability of failure on demand PFDavg, Spurious Trip Rate (STR) and Life Cycle Costs (LCCavg). A set of constraints related to maintenance costs have been established. These constraints imply specific maintenance strategies which improve the SIS performances and minimize the technical, economic and environmental risks related to spurious shutdowns. Validation of such an approach is applied to an Emergency Shutdown (ESD) of the blower section of an industrial facility (RGTE- In Amenas).Design/methodology/approachThe optimization of SIS performances is performed using the multi-objective genetic algorithm by minimizing their probability of failure on demand PFDavg, Spurious Trip Rate (STR) and Life Cycle Costs (LCCavg). A set of constraints related to maintenance costs have been established. These constraints imply specific maintenance strategies which improve the SIS performances and minimize the technical, economic and environmental risks related to spurious shutdowns. Validation of such an approach is applied to an Emergency Shutdown (ESD) of the blower section of an industrial facility (RGTE- In Amenas).FindingsA case study concerning a safety instrumented system implemented in the RGTE facility has shown the great applicability of the proposed approach and the results are encouraging. The results show that the selection of a good maintenance strategy allows a very significant minimization of the PFDavg, the frequency of spurious trips and Life Cycle Costs of SIS.Originality/valueThe maintenance strategy defined by the system designer can be modified and improved during the operational phase, in particular safety systems. It constitutes one of the least expensive investment strategies for improving SIS performances. It has allowed a considerable minimization of the SIS life cycle costs; PFDavg and the frequency of spurious trips.

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13

Manna, Giustino, Irina Kuzmina und Jaroslav Holy. „Outcomes of an international initiative for harmonization of low power and shutdown probabilistic safety assessment“. Nuclear Technology and Radiation Protection 25, Nr. 3 (2010): 222–28. http://dx.doi.org/10.2298/ntrp1003222m.

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Many probabilistic safety assessment studies completed to the date have demonstrated that the risk dealing with low power and shutdown operation of nuclear power plants is often comparable with the risk of at-power operation, and the main contributors to the low power and shutdown risk often deal with human factors. Since the beginning of the nuclear power generation, human performance has been a very important factor in all phases of the plant lifecycle: design, commissioning, operation, maintenance, surveillance, modification, decommissioning and dismantling. The importance of this aspect has been confirmed by recent operating experience. This paper provides the insights and conclusions of a workshop organized in 2007 by the IAEA and the Joint Research Centre of the European Commission, on Harmonization of low power and shutdown probabilistic safety assessment for WWER nuclear power plants. The major objective of the workshop was to provide a comparison of the approaches and the results of human reliability analyses and gain insights in the enhanced handling of human factors.

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14

Boustani, Ehsan, und Samad Khakshournia. „Enhancing Tehran Research Reactor safety through a Second Shutdown System: A probabilistic safety assessment“. Progress in Nuclear Energy 100 (September 2017): 380–88. http://dx.doi.org/10.1016/j.pnucene.2017.07.006.

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15

Yamano, H., S. Kubo, Y. Shimakawa, K. Fujita, T. Suzuki und K. Kurisaka. „Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor“. Science and Technology of Nuclear Installations 2012 (2012): 1–14. http://dx.doi.org/10.1155/2012/614973.

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As a next-generation plant, a large-scale Japan sodium-cooled fast reactor (JSFR) adopts a number of innovative technologies in order to achieve economic competitiveness, enhanced reliability, and safety. This paper describes safety requirements for JSFR conformed to the defense-in-depth principle in IAEA. Specific design features of JSFR are a passive reactor shutdown system and a recriticality-free concept against anticipated transients without scram (ATWS) in design extension conditions (DECs). A fully passive decay heat removal system with natural circulation is also introduced for design-basis events (DBEs) and DECs. In this paper, the safety design accommodation in JSFR was validated by safety analyses for representative DBEs: primary pump seizure and long-term loss-of-offsite power accidents. The safety analysis also showed the effectiveness of the passive shutdown system against a typical ATWS. Severe accident analysis supported by safety experiments and phenomenological consideration led to the feasibility of in-vessel retention without energetic recriticality. Moreover, a probabilistic safety assessment indicated to satisfy the risk target.

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Suparlina, Lily, Tukiran Surbakti, Surian Pinem und Purwadi Purwadi. „ANALYSES OF NEUTRON ABSORBER MATERIALS ON THE SAFETY PARAMETERS IN THE RSG-GAS REACTOR“. JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 23, Nr. 2 (14.06.2021): 69. http://dx.doi.org/10.17146/tdm.2021.23.2.6278.

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Shutdown system in RSG-GAS reactor is using neutron absorber. There are 3 kinds of absorber material in research reactors including Ag-In-Cd alloy, B4C, and Hf. In this works, analyses of different neutron absorbers on the main safety core parameters in the RSG-GAS research reactor are selected for analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, PPF and neutron flux . The RSG-GAS core silicide fuel is selected as the case study to verify calculations. A three-dimensional, four-group diffusion model is selected for core calculations. The well-known WIMSD-5B and Batan-3DIFF reactor codes are used to carry out these calculations. It is found that the largest shutdown margin is gained using the B4C; also the lowest PPF is gained using the Hf material. The maximum point power densities belong to the inside fuel regions surrounding the CIP (centre irradiation position), surrounded by control fuel elements, and the peripheral fuel elements beside the berrylium reflector. The greatest and least fluctuation of the point power densities are gained by using B4C and Ag-In-Cd alloy, respectively.

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17

Zhou, Hongyao, Haodong Liu, Yejing Li, Xiujun Yue, Xuefeng Wang, Matthew Gonzalez, Ying Shirley Meng und Ping Liu. „In situ formed polymer gel electrolytes for lithium batteries with inherent thermal shutdown safety features“. Journal of Materials Chemistry A 7, Nr. 28 (2019): 16984–91. http://dx.doi.org/10.1039/c9ta02341k.

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18

Liu, Enbin, Liuting Yang, Yong Jiang, Ping Tang, Jian Liu und Yuhang Yang. „Simulation on the Temperature Drop Rule of Hot Oil Pipeline“. Open Fuels & Energy Science Journal 6, Nr. 1 (30.12.2013): 55–60. http://dx.doi.org/10.2174/1876973x01306010055.

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The heat transfer equation of oil, pipe wall and soil, combining with the boundary condition, connection condition and initial conditions to be the differential equations which can simulate the temperature drop rule of hot oil pipeline. Then the numerical solution method is used to solve, constructed difference equations. By the gauss elimination method, the temperature changing rule of hot oil pipeline after shutdown can be obtained, so we can determine the safety shutdown time and the restart pressure.

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19

Dragffy, G. „The design of a highly reliable safety critical emergency shutdown system“. Reliability Engineering & System Safety 61, Nr. 3 (September 1998): 215–27. http://dx.doi.org/10.1016/s0951-8320(98)00012-x.

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20

Burgazzi, Luciano. „Analysis of solutions for passively activated safety shutdown devices for SFR“. Nuclear Engineering and Design 260 (Juli 2013): 47–53. http://dx.doi.org/10.1016/j.nucengdes.2013.03.020.

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21

Sammarco, John J. „Programmable Electronic and Hardwired Emergency Shutdown Systems: A Quantified Safety Analysis“. IEEE Transactions on Industry Applications 43, Nr. 4 (2007): 1061–68. http://dx.doi.org/10.1109/tia.2007.900477.

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22

Acharya, Govatsa, Fredrik Dehlin, Sara Bortot und Ignas Mickus. „INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR“. EPJ Web of Conferences 247 (2021): 07007. http://dx.doi.org/10.1051/epjconf/202124707007.

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Passive safety systems in a nuclear reactor allow to simplify the overall plant design, beside improving economics and reliability, which are considered to be among the salient goals of advanced Generation IV reactors. This work focuses on investigating the application of a self-actuated, gravity-driven shutdown system in a small lead-cooled fast reactor and its dynamic response to an initiating event. The reactor thermal-hydraulics and neutronics assessment were performed in advance. According to a first-order approximation approach, the passive insertion of shutdown assembly was assumed to be influenced primarily by three forces: gravitational, buoyancy and fluid drag. A system of kinematic equations were formulated a priori and a MATLAB program was developed to determine the dynamics of the assembly. Identifying the delicate nature of the balance of forces, sensitivity analysis for coolant channel velocities and assembly foot densities yielded an optimal system model that resulted in successful passive shutdown. Transient safety studies, using the multi-point dynamics code BELLA, showed that the gravity-driven system acts remarkably well, even when accounting for a brief delay in self-actuation. Ultimately the reactor is brought to a sub-critical state while respecting technological constraints.

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23

Pokrovsky, Pavel, und Vladimir Kudryavtsev. „Model of Emergency Shutdown System of TOKAMAK KTM“. Advanced Materials Research 1084 (Januar 2015): 689–93. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.689.

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The computer model of emergency shutdown (ESD) system of Tokamak has been developed. Xcos extension of the package Scilab of linux operating system was used for developing the model. The simulated system monitors the most ultimate in terms of the integrity of the preproduction equipment and personnel safety parameters and provides an opportunity to prevent accidents. In the accidents occur the system executes algorithms of protective effects providing the complex transfer to a safe state, which allows to reduce consequences of possible accidents.

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Li, Liang, Xiuli Du, Rong Pan, Xiuyun Zhu und Haiyan Luan. „Research on Improved Seismic Instrumentation System for Nuclear Power Plants“. Energies 14, Nr. 14 (14.07.2021): 4262. http://dx.doi.org/10.3390/en14144262.

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According to the requirements of nuclear safety regulations, nuclear power plants must be equipped with seismic instrumentation systems, which are mainly used for monitoring alarm and automatic shutdown alarm during an earthquake. Both the second and third generation NPPs adopt Peak Ground Acceleration (PGA). However, among the seismic acceleration characteristics, isolated and prominent single high frequency acceleration peaks have no decisive influence on the seismic response. Especially when the earthquake monitoring alarm is at 1 out of 7, it is likely to cause a false alarm or false shutdown. In addition, it usually takes one month or more for the NPPs to restart after the shutdown. In this paper, an improved seismic instrumentation system based on the existing system is proposed. For high intensity areas, three components resultant acceleration is used to judge the 2 out of 4 logic of the automatic seismic trip system(ASTS). For low intensity areas, the seismic failure level is evaluated quickly by using three components resultant acceleration, seismic instrument intensity, cumulative absolute velocity, floor response spectrum and other multi-parameters, avoiding unnecessary and long-term shutdown inspection.

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Chen, Hui, Youlong Fang, Xingwei Liu, Xiaoyu Jiang, Faping Zhong, Hanxi Yang, Xinping Ai und Yuliang Cao. „A controllable thermal-sensitivity separator with an organic–inorganic hybrid interlayer for high-safety lithium-ion batteries“. Materials Chemistry Frontiers 5, Nr. 5 (2021): 2313–19. http://dx.doi.org/10.1039/d0qm01061h.

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The PAN/EVA@SiO₂/PAN (PESP) separator fabricated by electrospinning approach exhibits a proper shutdown function at approximately 120 °C, which can greatly improve the safety of lithium-ion batteries.

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Brannigan, Vincent M. „Alice's Adventures in Volcano Land: The Use and Abuse of Expert Knowledge in Safety Regulation“. European Journal of Risk Regulation 1, Nr. 2 (Juni 2010): 107–13. http://dx.doi.org/10.1017/s1867299x00000192.

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As a volcano refugee in Frankfurt, it was rather interesting to see a slow motion regulatory science disaster taking place. On April 14 2010 the Icelandic volcano Eyjafjallajökull erupted sending millions of tons of ash into the upper atmosphere. The ash cloud, blown by the prevailing winds, moved down over northern Europe. European air traffic authorities, following well established and widely published safety protocols, began shutting down the air transport system due to the well known hazard of volcano ash. The shutdown lasted 6 days and soon became an unequal political contest between airline money on the one side and regulatory science on the other. In a classic case of shooting the messenger bringing bad news the responsible airline parties tried to shift the blame for shutdown to the regulators, while nervous governments quailed before the bullying of the airline executives.

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Oussedik, Sam, Luigi Zagra, Gee Yen Shin, Rocco D’Apolito und Fares S. Haddad. „Reinstating elective orthopaedic surgery in the age of COVID-19“. Bone & Joint Journal 102-B, Nr. 7 (Juli 2020): 807–10. http://dx.doi.org/10.1302/0301-620x.102b7.bjj-2020-0808.

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The transition from shutdown of elective orthopaedic services to the resumption of pre-COVID-19 activity presents many challenges. These include concerns about patient safety, staff safety, and the viability of health economies. Careful planning is necessary to allow patients to benefit from orthopaedic care in a safe and sustainable manner. Cite this article: Bone Joint J 2020;102-B(7):807–810.

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Manna, Giustino, Jaroslav Holy und Irina Kuzmina. „Human reliability analysis in low power and shut-down probabilistic safety assessment: Outcomes of an international initiative“. Nuclear Technology and Radiation Protection 27, Nr. 2 (2012): 189–97. http://dx.doi.org/10.2298/ntrp1202189m.

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Since the beginning of the nuclear power generation, human performance has been a very important factor in all phases of the plant lifecycle: design, commissioning, operation, maintenance, surveillance, modification, and decommissioning. This aspect has been confirmed by the operating experience. A workshop was organized by the IAEA and the Joint Research Centre of the European Commission, on Harmonization of low power and shutdown probabilistic safety assessment for WWER nuclear power plants. One of the major objectives of the Workshop was to provide a comparison of the approaches and results of human reliability analyses for WWER 440 and WWER 1000, and gain insights for future application of human reliability analyses in Low Power and Shutdown scenarios. This paper provides the insights and conclusions of the workshops concerning human reliability analyses and human factors.

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Ivanov, V. P., und E. B. Kablova. „Control of the Times of Engine Shutdown by the Launch Safety Criterion“. IFAC Proceedings Volumes 37, Nr. 6 (Juni 2004): 275–79. http://dx.doi.org/10.1016/s1474-6670(17)32186-9.

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30

Kim, Jung-Wun, und Chan-Geun Park. „Fire Protection Regulations for Ensuring Fire Safety during Decommissioning Nuclear Power Plants in Korea“. Fire Science and Engineering 34, Nr. 3 (30.06.2020): 134–40. http://dx.doi.org/10.7731/kifse.c3462cff.

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Nuclear power plants (NPPs) in Korea are required to be maintained using a defense in-depth approach to prevent leakage of radioactive substances outside the plant and allow safe shutdown in the event of a fire. Periodic testing must be conducted to ensure that the fire protection facilities perform as required by the laws for various nuclear reactor types. In June 2017, for the first time in Korea, a nuclear plant, Kori Unit 1, was permanently shut down. It was prepared for decommissioning in accordance with the fire protection regulations imposed by the regulatory body. However, a standard protocol is necessary for systematically establishing the fire protection program for decommissioning of NPPs in the future. Therefore, the nuclear legal systems of countries with many operating nuclear power plants, such as the United States, Japan, Canada, and various European countries, were reviewed and guidelines for establishing a fire protection program for decommissioning NPPs was suggested; the fire protection requirements stated by Reg Guide 1.191 (Decommissioning fire protection program for NPPs during decommissioning and permanent shutdown) were used as a model. Suggestions for establishing legal regulations to optimize fire protection programs and secure basic technology for decommissioning NPPs were also made.

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Duhamel, Isabelle, Mariya Brovchenko, Jean-Baptiste Clavel, Matthieu Duluc, Raphaëlle Ichou, Luiz Leal, Nicolas Leclaire und Wilfried Monange. „THE PRINCESS PROJECT: FROM DIFFERENTIAL TO INTEGRAL EXPERIMENTS“. EPJ Web of Conferences 247 (2021): 20002. http://dx.doi.org/10.1051/epjconf/202124720002.

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Following the shutdown of the CEA Valduc experimental facilities, where, for more than 50 years, IRSN used to perform experiments related to criticality safety, IRSN initiated a new project named PRINCESS (PRoject for IRSN Neutron physics and Criticality Experimental data Supporting Safety). The objective is to continue collecting experimental data necessary for the IRSN missions in nuclear safety. For this purpose, collaborations with various national and international laboratories have been established. The PRINCESS project covers various nuclear physics fields from nuclear data to criticality-safety and reactor physics providing information to both differential and integral data improvements.

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Nissan, Ephraim. „An Overview of AI Methods for in-Core Fuel Management: Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)arranging New and Partly Spent Fuel“. Designs 3, Nr. 3 (15.07.2019): 37. http://dx.doi.org/10.3390/designs3030037.

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An important aspect of managing a nuclear reactor is how to design refuellings, and from the 1980s to the present different artificial intelligence (AI) techniques have been applied to this problem. A section of the reactor core resembles a symmetrical grid; long fuel assemblies are inserted there, some of them new, some of them partly spent. Rods of “burnable poisons” dangle above, ready to be inserted into the core, in order to stop the reactor. Traditionally, manual design was made by shuffling positions in the grid heuristically, but AI enabled to automatically generate families of candidate configurations, under safety constraints, as well as in order to optimize combustion, with longer cycles of operation between shutdown periods, thus delaying the end-of-cycle point (except in France, where shutdown is on an annual basis, and Canada, where individual fuel assemblies are replaced, with no need for shutdown for rearranging the entire batch). Rule-based expert systems, the first being FUELCON,1 were succeeded by projects combining neural and rule-based processing (a symbolic-to-neural compilation of rules we did not implement), and later on, genetic algorithms in FUELGEN.2 In the literature, one also comes across the application of fuzzy techniques, tabu search, cellular automata and simulated annealing, as well as particle swarms. Safety regulations require simulating the results using a parameter prediction tool; this is done using either nodal algorithms, or neural processing.

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Leonardo, Alfeus, Endra Joelianto und Sutanto Hadisupadmo. „Perancangan Safety Shutdown System pada Kepala Sumur Minyak dengan Menggunakan Analisis Pemodelan Petrinet“. Jurnal Otomasi Kontrol dan Instrumentasi 7, Nr. 1 (14.08.2015): 9. http://dx.doi.org/10.5614/joki.2015.7.1.2.

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34

Morin, B., C. Hu, P. Khokhlov, J. Kaschmitter und S. J. Cho. „Safety Testing with Nonwoven Nanofiber Separators: Comparing Shutdown Separators to Thermally Stable Separators“. ECS Transactions 72, Nr. 12 (21.09.2016): 1–12. http://dx.doi.org/10.1149/07212.0001ecst.

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35

Varde, P. V., Tej Singh, Tanay Mazumdar und Arihant Jain. „Risk-based approach towards design evaluation and re-assessment of shutdown safety margin“. Life Cycle Reliability and Safety Engineering 7, Nr. 4 (03.09.2018): 215–34. http://dx.doi.org/10.1007/s41872-018-0047-7.

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36

Liu, Shi, Heng Liang Zhang, Yan Zhou und Dan Mei Xie. „The Analytical Research and Development of On-Line Monitoring Models of Thermal State for Turbine Rotor“. Advanced Materials Research 744 (August 2013): 105–9. http://dx.doi.org/10.4028/www.scientific.net/amr.744.105.

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Steam turbine units are required to start up and shut down as fast as possible to improve economy and load-response ability of the units under the qualification of safety. it is important to monitor and control thermal state in turbine during operation, especially during the process of start-up and shutdown. Thermal stresses in turbine rotor in thermal power plants are the limiting factors for rapid startup, shutdown or load change. In this paper the online calculation models of temperature and thermal stress for a two-dimensional axis-symmetric object are obtained after disposing of the nonlinear factor such as temperature-dependent properties by a transformation. The model gained can be used to analyze thermal states in thick-walled components, monitoring and control online.

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Kamyab, Shahabeddin, Faramarz Yousefpour, Alireza Yousefi und Kaveh Karimi. „Effects of shutdown period extension on core damage frequency“. International Journal of System Assurance Engineering and Management 8, Nr. 3 (13.06.2017): 612–24. http://dx.doi.org/10.1007/s13198-017-0643-3.

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38

Tang, Hai Jun, und Hong Yu Yao. „Failure Analysis on a Counterweight Assembly of an Aeroengine“. Advanced Materials Research 339 (September 2011): 342–48. http://dx.doi.org/10.4028/www.scientific.net/amr.339.342.

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The paper presents a failure analysis on a counterweight assembly installed on crank shaft which resulted in an in-flight shutdown of a piston aeroengine. The counterweight assembly failure includes counterweight block material loss and fractured washer which is the most crucial part for in-flight shutdown in this type of aeroengine. Macro observation, fractography analysis, metallography analysis and hardness test were conducted on the failed counterweight assembly. The result shows that failure mechanism of counterweight block and washer is fatigue. The washer failure is likely due to inappropriate heat treatment process and continuous impact in flight by slightly tilted roller. Counterweight material loss is attributed to stress concentration, low structure strength and impact came from the tilted roller. Finally some safety suggestion on design and maintenance is given.

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Gao, Yi Ping, Jun Le, Xiao Cheng Sheng und Xiao Wei Zhang. „Close-Packed Al₂O₃ Nanoparticles/Waterborne Polyurethane Layer-Coated Polyethylene Separators for Lithium-Ion Batteries“. Advanced Materials Research 724-725 (August 2013): 823–28. http://dx.doi.org/10.4028/www.scientific.net/amr.724-725.823.

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Separator shutdown by interrupting the transmission of lithium ions to terminate the battery reaction is a valid safety mechanism for preventing thermal runaway reactions in lithium ion batteries. Yet the cell temperature continues rising after the shutdown, the separator need sufficient thermal stability to physically isolate the electrodes. To reduce the thermal shrinkage of polyethylene (PE) separators, a fresh composite separator is developed by introducing alumina (Al2O3) nanoparticles/waterborne polyurethane (WPU) layer on one side of the pristine PE separator via casting process. The microporous structure of the composite separator is supposed to be a significant consideration for the cell performance, which is confirmed by the scanning electron microscope. Compared with the pristine PE separator, the thermal shrinkage of the novel separator improved markedly with an acceptable decline in air permeability and ion conductivity.

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JÓŹWIK, Roman. „THE USE OF NUCLEAR ENERGY FOR MILITARY AND CIVILIAN PURPOSES SAFETY IN THE NUCLEAR POWER INDUSTRY“. Journal of Science of the Gen. Tadeusz Kosciuszko Military Academy of Land Forces 185, Nr. 3 (01.06.2017): 106–23. http://dx.doi.org/10.5604/01.3001.0010.5127.

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The purpose of the article was to gather the basic information about the mechanism be-hind nuclear energy formation and the types of reactors, already built worldwide or poten-tially planned for construction in the near future, and to present the history of the begin-nings of nuclear power in Poland. The issues of the safety of reactors, independent safety assurance systems and systems for emergency shutdown of a reactor are discussed in more detail. The problem of responsibility for the safety of nuclear equipment is also ex-amined, including the relevant authority and method for such safety inspection. The initia-tives taken in Poland in connection with the programme for the nuclear power industry are also described.

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Zhang, Shao Bo, Bi Xiong Luo, Xu Bin Qiao, Juan Chen und Xiao Dong Wang. „FeedWater System Transient Analysis of Nuclear Power Station“. Advanced Materials Research 347-353 (Oktober 2011): 1557–60. http://dx.doi.org/10.4028/www.scientific.net/amr.347-353.1557.

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Nuclear power station has high safety requirements, and the safety systems related to the nuclear island must be checked by hydraulic calculation. In the conventional island, the safe shutdown of the nuclear island most closely relates to the feedwater system, which determines the quantity and quality of the feedwater supply to the steam generator. In this paper, feedwater evolution in case of steamline break will be presented by using Flowmaster hydraulic software, and the results was used as the input for the analysis of security assessment in the nuclear island.

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Bley, D. C., und W. B. Reuland. „Application of a process flow model to a shutdown nuclear plant probabilistic safety assessment“. Reliability Engineering 17, Nr. 4 (Januar 1987): 241–53. http://dx.doi.org/10.1016/0143-8174(87)90090-4.

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43

Wang, Hai Tao, und Yun Chun Xia. „The Thermal Stress of a Domestic 300MW Steam Turbo Unit during its Startup and Shutdown“. Applied Mechanics and Materials 275-277 (Januar 2013): 87–93. http://dx.doi.org/10.4028/www.scientific.net/amm.275-277.87.

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The simulation system on the thermal stress of the rotor during startup & shutdown for a domestic 300MW steam turbo unit, by the simulation, the surface of the shaft was suffered a crushing stress, but it was a pulling stress when a unit shutdown. The max thermal stress & the max combined stress produced on the rotor of a medium pressure cylinder was about 16% bigger than those on the rotor of the high pressure cylinder when they had the same increase rate of temperature. When thought from economics & safety, the optimal temperature-increase-rate of the rotor was 1.6°C/min when the unit startup at cold state, but it was 1. 8°C/min when started up and shut down the unit at hot state, it’s optimal for slipping-parameter and the optimal temperature-decease-rate of the rotor was 0.85°C/min.

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Frolov, O. E. „Choosing the safety indicators values of emergency shutdown (ESD) systems depending on the generalized safety level of a process facility“. Automation, Telemechanization and Communication in Oil Industry, Nr. 11 (2019): 27–32. http://dx.doi.org/10.33285/0132-2222-2019-11(556)-27-32.

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45

Xie, Binxuan, Shimou Chen, Yong Chen und Lili Liu. „Self-shutdown function induced by sandwich-like gel polymer electrolytes for high safety lithium metal batteries“. RSC Advances 11, Nr. 23 (2021): 14036–46. http://dx.doi.org/10.1039/d1ra02641k.

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46

Zhao, Bin, Jun Hao Li, Jing Quan Shen und Guo Zhong Wang. „The Analysis on Circulating Fluidized Bed Boiler Heat Tube Failure“. Advanced Materials Research 291-294 (Juli 2011): 1679–84. http://dx.doi.org/10.4028/www.scientific.net/amr.291-294.1679.

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Boiler heat tube failure is a long-term technical problem plaguing the production of electricity. The research on how to prevent failure of boiler heat tubes has practical significance. In this paper, select the type of the Tangshan Dong fang power plant SG-490/13.8-M572 CFB boiler as the research object, part by pressure, failure type, and run-time statistics on the heat tubes failure of two boilers throught the collation and analysis on records, the basic rules of the failure are found out, statistics show that the water wall and super heater tubes explosion causes boiler shutdown time accounted for unplanned boiler shutdown time about 82%, small power generating capacity of about 11% of the total time. Finally, relevant technical strategies including improving maintenance quality and strengthening boilers regular inspection are proposed, the unplanned outage of units is radically reduced, and the safety and reliability of boiler operation is comprehensively improved.

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Kang, Ji Su, und Jae Hak Cheong. „Characteristics of Radioactive Effluent Releases from Pressurized Water Reactors after Permanent Shutdown“. Energies 13, Nr. 10 (12.05.2020): 2436. http://dx.doi.org/10.3390/en13102436.

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In order to expand our understanding of the characteristics of radioactive effluent from nuclear power plants under decommissioning, which have not been systematically investigated, a series of source term models of radioactive effluent after permanent shutdown has been established based upon theoretical reasoning on the design and operation features of plants and derived in terms of fifteen arguments. Comprehensive radioactive effluent data have been collected and profiled from twenty-eight decommissioning pressurized water reactors, and annual trends of effluent from each plant have been quantitatively analyzed using Mann-Kendall statistical test. In addition, the characteristics of collected effluent data have been qualitatively interpreted based upon arguments newly proposed in this study. Furthermore, potential decreasing of dilution factor for liquid effluent and its safety implications are identified. The source term models and verified characteristics of radioactive effluent after permanent shutdown developed in this study can be used for establishing more efficient discharge monitoring program for decommissioning authorization.

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Ma, Qiu Rong, Yang Li und Kun Yang. „Study on the Test of Fatigue Life Prediction for X80 Line Pipe“. Applied Mechanics and Materials 692 (November 2014): 387–90. http://dx.doi.org/10.4028/www.scientific.net/amm.692.387.

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This paper researched the test of fatigue crack propagation of grade X80 submerged arc welded pipes. According to the test results, analyzed and calculated the fatigue life of submerged arc welded pipes for X80 with half elliptical crack defects at the simulated work condition of shutdown. On a single simulated work condition, the fatigue life of submerged arc welded pipes for X80 with Ф1219×22.0mm is 62 years, which had enough safety margin for fatigue life.

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Volkanovski, Andrija, und Andrej Prošek. „Delayed Station Blackout Event and Nuclear Safety“. Science and Technology of Nuclear Installations 2015 (2015): 1–9. http://dx.doi.org/10.1155/2015/192601.

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The loss of off-site power (LOOP) event occurs when all electrical power to the nuclear power plant from the power grid is lost. Complete failure of both off-site and on-site alternating current (AC) power sources is referred to as a station blackout (SBO). Combined LOOP and SBO events are analyzed in this paper. The analysis is done for different time delays between the LOOP and SBO events. Deterministic safety analysis is utilized for the assessment of the plant parameters for different time delays of the SBO event. Obtained plant parameters are used for the assessment of the probabilities of the functional events in the SBO event tree. The results show that the time delay of the SBO after the LOOP leads to a decrease of the core damage frequency (CDF) from the SBO event tree. The reduction of the CDF depends on the time delay of the SBO after the LOOP event. The results show the importance of the safety systems to operate after the plant shutdown when the decay heat is large. Small changes of the basic events importance measures are identified with the introduction of the delay of the SBO event.

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Ušpuras, E. „State of the Art of the Ignalina RBMK-1500 Safety“. Science and Technology of Nuclear Installations 2010 (2010): 1–11. http://dx.doi.org/10.1155/2010/102078.

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Ignalina NPP is the only nuclear power plant in Lithuania consisting of two units, commissioned in 1983 and 1987. Unit 1 of Ignalina NPP was shut down for decommissioning at the end of 2004 and Unit 2 is to be operated until the end of 2009. Both units are equipped with channel-type graphite-moderated boiling water reactors RBMK-1500. The paper summarizing the results of deterministic and probabilistic analyses is developed within 1991–2007 by specialists from Lithuanian Energy Institute. The main operational safety aspects, including analyses performed according the Ignalina Safety Improvement Programs, development and installation of the Second Shutdown System and Guidelines on Severe Accidents Management are discussed. Also the phenomena related to the closure of the gap between fuel channel and graphite bricks, multiple fuel channel tube rupture, and containment issues as well as implication of the external events to the Ignalina NPP safety are discussed separately.

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