Gotowe bibliografie tematyczne / Passive safety

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Gotowa bibliografia na temat „Passive safety”

Autor: Grafiati

Data publikacji: 4 czerwca 2021

Data aktualizacji: 1 lutego 2022

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Artykuły w czasopismach na temat "Passive safety"

Schüler, Lars, i Franz Fürst. "Passive Safety". ATZextra worldwide 12, nr 1 (wrzesień 2007): 56–61. http://dx.doi.org/10.1365/s40111-007-0011-4.

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Speth, Bernhard, Markus Pfestorf, Jürgen Lescheticky, Till Laumann i Heinrich Werner. "Passive Safety". ATZextra worldwide 13, nr 8 (listopad 2008): 120–25. http://dx.doi.org/10.1365/s40111-008-0115-5.

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Broscheit, Michael, Jose David Martin Rodriguez, Klaus Semmler i Christian Hess. "PASSIVE SAFETY". ATZextra worldwide 15, nr 11 (styczeń 2010): 208–15. http://dx.doi.org/10.1365/s40111-010-0263-2.

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Sato, Takashi, Makoto Akinaga i Yoshihiro Kojima. "ICONE15-10618 TWO TYPES OF A PASSIVE SAFETY CONTAINMENT FOR A NEAR FUTURE BWR WITH ACTIVE AND PASSIVE SAFETY SYSTEMS". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_339.

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Schwarz, Thomas, Andreas Tschritter, Tobias Köppel, Andreas Meier, Markus Geiss i Arturo Llamazares. "ACTIVE AND PASSIVE SAFETY". ATZextra worldwide 15, nr 5 (czerwiec 2010): 72–75. http://dx.doi.org/10.1365/s40111-010-0203-1.

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Lachmayer, Roland, i Flavio Friesen. "Headlamps and passive safety". ATZ worldwide 103, nr 7-8 (lipiec 2001): 2–5. http://dx.doi.org/10.1007/bf03226796.

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Reichenbach, Michael. "Active and Passive Safety". ATZ worldwide 118, nr 7-8 (lipiec 2016): 14–15. http://dx.doi.org/10.1007/s38311-016-0094-5.

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Тарасова, E. Tarasova, Дорохин i S. Dorokhin. "ACTIVE AND PASSIVE SAFETY VEHICLES". Alternative energy sources in the transport-technological complex: problems and prospects of rational use of 2, nr 2 (17.12.2015): 713–18. http://dx.doi.org/10.12737/19537.

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The article describes the basic elements of active and passive safety, as well as their impact on the consequences of road accidents. Shows the interaction of systems of active and passive safe- ty in the event of a frontal collision, side collision, rear impact, rollover

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Piet, S. J. "Inherent/Passive Safety for Fusion". Fusion Technology 10, nr 3P2B (listopad 1986): 1191–96. http://dx.doi.org/10.13182/fst86-a24892.

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Inai, Nobuhiko, Hiromichi Nei i Toshiaki Kumada. "Expansion of Passive Safety Function." Transactions of the Japan Society of Mechanical Engineers Series B 60, nr 575 (1994): 2573–78. http://dx.doi.org/10.1299/kikaib.60.2573.

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Rozprawy doktorskie na temat "Passive safety"

Richard, R. W. "Driver risk taking in response to perceived differences in passive safety". Thesis, Cranfield University, 1985. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.356256.

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Thomas, Gareth, i gareth e. thomas@hotmail com. "Compatibility and structural interaction in passenger vehicle collisions". RMIT University. Aerospace, Mechanical and Manufacturing Engineering, 2006. http://adt.lib.rmit.edu.au/adt/public/adt-VIT20070122.125652.

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This research contributes to the existing body of knowledge relating to crash compatibility (the minimisation of injury risk faced by all participants involved in a collision in traffic). The research focuses on the topic of structural interaction in collisions involving passenger vehicles, a phenomenon describing the efficiency of energy dissipation within existing deformation-zones of a passenger vehicle during a collision. A new definition for structural interaction was developed and several metrics to evaluate structural interaction and compatibility in car-to-car collisions were proposed, based on the commonly known Equivalent Energy Speed (EES) metric. The new EES metrics describe equivalent closing velocities for a given collision based on the energy dissipated within the front-ends (EESFF) and the entire structure (EESVV) of both vehicles involved in a head-on collision. These metrics form the basis of the new knowledge generated by this research. Additionally, a new method was developed to measure the amount of energy dissipated through structural deformation in a collision, based on accelerometer readings. This method was applied to several experimental and simulationbased car-to-car collisions and the validity of the method was proven. Based on the energy dissipation which occurred in the car-to-car collisions analysed, the degree of compatibility reached and the level of structural interaction which occurred in each collision was evaluated by applying the newly developed EESFF and EESVV metrics. Thie research also investigates the assessment of vehicles' structures in a standardized procedure with a view to improving structural interaction in the real-world. Several fixed barrier crash tests have been proposed in different configurations and with different assessment criteria. All assessments aim to evaluate the geometrical characteristics of the front-ends of passenger vehicles. A set of factors required from a compatilibility assessment focused on assessing vehicle geometry were identified. The proposed compatibility assessment procedures were evaluated based on their ability to predict the potential for structural interaction offered by passenger vehicles.

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Mansfield, Julie Ann. "Investigation of Child Restraint System (CRS) Misuse: Passive and Active Educational Interventions". The Ohio State University, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu154505928327915.

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Koukoulas, Effy. "Post-approval drug safety: moving from passive to active pharmacovigilance in Canada". Thesis, McGill University, 2013. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=116890.

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Adverse drug reactions (ADRs) present heavy burdens for the public health care system, and current pharmacovigilance activities are challenged by the under-reporting of ADRs in spontaneous reporting systems and a lack of incentive for industry to conduct rigorous post-approval research. As part of a new lifecycle approach to drug regulation, Health Canada recently announced plans to develop a new health product vigilance framework that will allocate drug safety resources using prioritization schemes focused on higher risk. These plans include the development of official policy requirements for industry to submit formal Risk Management Plans to Health Canada. This thesis argues that this approach is limited by lack of transparency and standardization, burdens on health care practitioners, and a risk of causing treatment disparities. This thesis presents alternative measures for improving post-market drug safety surveillance through initiatives for enhancing ADR data collection systems. These include the use of electronic health records for automated reporting by health care professionals, the screening of health-related social media sites for ADR reports, and the use of internet-based prescription monitoring systems to solicit ADR reports. This thesis also proposes options for improved post-approval research efforts. These include enhanced legislative authority for Health Canada to mandate post-market research commitments to drug sponsors as conditions of approval, offering extensions on data protection to sponsors in exchange for comparative effectiveness research, implementing mandatory industry-sourced funding for objective third-party research, and ensuring that the Drug Safety and Effectiveness Network contains adequate patient representation. In the current context of limited health care resources, these alternatives merit further consideration, including consultation and validation with relevant stakeholders, in order determine the most value-added methods for improving drug safety surveillance.
Les manifestations indésirables dues aux médicaments représentent une lourde charge pour le la santé publique d'autant plus que les activités actuelles de pharmacovigilance sont limitées, d'une part par le fait qu'un bon nombre de rapports spontanés ne sont pas comptabilisés dans les différentes bases de données et d'autre part parce qu'il n'existe pas suffisamment d'incitatifs pour encourager l'industrie à mener des recherches systématiques après qu'un médicament ait été approuvé. Dans le cadre d'une nouvelle approche de la réglementation des médicaments basée sur le cycle de vie de ceux-ci, Santé Canada a récemment annoncé son intention de développer un nouveau cadre sur la surveillance des produits de santé qui permettra d'allouer à l'innocuité des médicaments les ressources selon des priorités établies en fonction d'un risque plus élevé. Ce projet inclut le développement d'une politique officielle pour exiger de l'industrie qu'elle soumette des plans concrets de gestion du risque à Santé Canada. Ce mémoire soutient que cette approche contient des limitations causées par un manque de transparence et d'uniformisation, qu'elle représente un fardeau additionnel pour les professionnels de la santé et qu'elle risque de causer des disparités dans le traitement des données recueillies.Ce mémoire présente des mesures alternatives visant à améliorer le suivi au sujet de l'innocuité des médicaments une fois que ces derniers sont sur le marché, en utilisant des initiatives visant à améliorer les systèmes de collection des rapports de manifestations indésirables. Ces mesures incluent l'utilisation de registres de santé informatisés pour les rapports automatisés provenant des professionnels de la santé, le criblage de sites Internet de type médias sociaux ayant un lien avec les rapports de manifestations indésirables et l'utilisation de systèmes de surveillance Internet pour solliciter les rapports de manifestations indésirables. Ce mémoire propose également diverses options pour l'amélioration des efforts de recherche une fois le médicament approuvé. Les propositions incluent une autorité législative plus grande pour Santé Canada pour inclure comme condition d'approbation des engagements fermes de la part des fabricants de médicaments d'effectuer de la recherche post-commercialisation, offrir aux compagnies des extensions pour la protection de données en échange de recherche comparative sur l'efficacité, la mise en œuvre obligatoire de sources de financement provenant de l'industrie pour des recherches indépendantes effectuées par un tiers-parti et assurer que le Réseau sur l'innocuité et l'efficacité des médicaments contient une représentation adéquate des patients. Dans le contexte actuel où les ressources allouées au système de santé sont limitées, ces alternatives méritent qu'on s'y attarde davantage, et que l'on inclue la consultation et la validation avec les parties concernées, dans le but de déterminer les méthodes à plus grande valeur ajoutée pour l'amélioration de la surveillance de l'innocuité des médicaments.

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Gkorogias, Panagiotis, i Susanna Gerges. "Concrete sandwich element design in terms of Passive Housing recommendations and moisture safety". Thesis, KTH, Byggvetenskap, 2015. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-168734.

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In this thesis project a concrete sandwich wall element of 250 mm insulation of Kooltherm has been resulted to have U-values and ψ-values closer to the passive housing recommendations. However, by using 180 mm thick insulation, no significant difference in the annual energy consumption is observed. Using a metal sheet in the window connection and small concrete brackets, low thermal bridge values are achieved. Low thermal bridge coefficient values were also observed with thick insulation in the foundation and the roof structure, although, it is impossible to achieve values below 0,01 W/mK in the corner connections. Airtightness of the building envelope is more important than the thickness of the wall in the energy consumption simulations. Therefore, the thermal bridging and the U-values of the wall are, in most cases, dependent on the thickness of the element. No conclusions on the structural reliability of the solutions can be extracted from this thesis project. In order to conclude the statements above, this thesis project has been focused on the evaluation and design of a concrete sandwich wall panel. The design of the wall element, including its reinforcement and connectors, while achieving values according to passive housing regulations, is the initial goal of this project. Subsequently, connections between the building components and the wall element are analyzed and designed through several simulations according to the passive housing regulations respectively. Simulation tests took place in Sweco Structures AB offices with the valuable contribution of experts. An existing building project was used and evaluated in order to present the simulation results in a more realistic manner. Several insulation materials have been tested for the thermal and moisture reliability. Using the existing building as a base for information, energy simulations generated the energy consumption results in order to compare different wall thicknesses, and thermal bridging effects. This project is inspired by the needs of building sustainability and efficiency, which has become a significant part of the worldwide effort on reducing the energy consumption on the planet. Regulations regarding building technology have been completely changed and adjusted in the passive housing design. Particular effort has been put on the commercial and multi-residential buildings, in which the energy consumption is usually higher than in small family houses. Concrete sandwich wall panels have been introduced in the building market as an alternative and more efficient way of constructing. Prefabrication has been proved to be less time consuming, although issues on the thermal behavior appear in this kind of structure. The evaluation of the thermal efficiency of the concrete sandwich wall elements has been a significant issue in the civil engineering society and research.

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Eul, Ryan C. "The impact of passive safety systems on desirability of advanced light water reactors". Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41267.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering; and, (S.M.)--Massachusetts Institute of Technology, Engineering Systems Division, Technology and Policy Program, 2006.
Includes bibliographical references (leaves 121-123).
This work investigates whether the advanced light water reactor designs with passive safety systems are more desirable than advanced reactor designs with active safety systems from the point of view of uncertainty in the performance of safety systems as well as the economic implications of the passive safety systems. Two advanced pressurized water reactors and two advanced boiling water reactors, one representing passive reactors and the other active reactors for each type of coolant, are compared in terms of operation and responses to accidents as reported by the vendors. Considering a simplified decay heat removal system that utilizes an isolation condenser for decay heat removal, the uncertainty in the main parameters affecting the system performance upon a reactor isolation accident is characterized when the system is to rely on natural convection and when it is to rely on a pump to remove the core heat. It is found that the passive system is less certain in its performance if the pump of the active system is tested at least once every five months. In addition, a cost model is used to evaluate the economic differences and benefits between the active and passive reactors. It is found that while the passive systems could have the benefit of fewer components to inspect and maintain during operation, they do suffer from a larger uncertainty about the time that would be required for their licensing due to more limited data on the reliability of their operation. Finally, a survey among nuclear energy experts with a variety of affiliations was conducted to determine the current professional attitude towards these two competing nuclear design options. The results of the survey show that reactors with passive safety systems are more desirable among the surveyed expert groups. The perceived advantages of passive systems are an increase in plant safety with a decrease in cost.
by Ryan C. Eul.
S.M.

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Paladdino, Domenico. "Investigations of passive safety systems in LWRs : melt coolability with bottom coolant injection, light gas effects on a passive containment cooling system". Doctoral thesis, KTH, Energy Technology, 2004. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-3816.

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The key objectives in introducing passive features in thesafety systems for Light Water Reactor (LWR) are to increasetheir reliability, to simplify the design of the plants and toimprove performance and economics. Component and integralsystem tests in scaled facilities are required for optimizingthe design and for certification of these safety systems.Experimental programs are also needed for a betterunderstanding of all significant physical phenomena on thebasis of which the passive safety systems function.

In thefirst partof the thesis the results of an investigationon melt coolability with bottom coolant injection arepresented. Ex-vessel coolability of a molten pool and/or debrisis, perhaps the most vexing remaining issue, needingresolution, in the beyond the design-base safety assessment forthe current and the future light water reactor plants. Latephase of the progression of a severe accident is associatedwith corium-melt discharge from the Reactor Pressure Vessel(RPV) and its relocation on the concrete basemat in the form ofa debris bed consisting of liquid/particulate corium. The coredebris generates decay heat and attacks the concrete basematand the containment structures and continues to do so, untilthe coolability of debris bed is achieved. Failure to assurethe coolability of the debris bed is tantamount to the failureto assure the termination of the severe accident. A researchprogram named DECOBI was developed at the Nuclear Power Safetydivision of the Royal Institute of Technology to study thecoolability of melt pools with bottom coolant injection whichoccurs passively through nozzles embeddedin concrete whichopen after ablation of a predetermined depth of concretebasemat. The research objective was to explore the mechanism ofhigh heat transfer and in particular the large scale porosityformation. In the DECOBI program first a series of experimentswere performed at low temperature, by using transparent pooland coolant that allows the visualization of the flow patternduring the pool-coolant interaction. The parameters governingthe early stages of the coolant phase change and dispersion inthe pool are identified through these visual experiments.

Experiments were performed also with metallic (Pb) andbinary oxide simulants (CaO-B₂O₃, MnO-TiO₂, CaO-WO₃), such that a substantial range of parametersinfluencing coolant-melt interaction and the subsequent debrisstructure was investigated. The molten metal (Pb) has highconductivity and low viscosity, which results in a high heattransfer rate and mixing of pool and coolant. The coolingprocess occurs rapidly and the porosity, after solidificationhas a fine and quite uniform structure. On the contrary theoxide mixture CaO-B₂O₃has high temperature, low conductivity, highviscosity and glassy material structure, which resulted inlower heat transfer rate and more difficult pool-coolantmixing. In the coolant-contacted regions, directly above thenozzle locations, an interconnected branched channel typeporosity was obtained. These regions had high porosity and theyquenched due to the continuous passage of coolant, even longafter solidification. The other regions did not developporosity because the crust formed outside the quenched regions,prevented the direct contact of coolant with these regions.These regions, however, could conduct heat to the adjacent coldregions and cooled eventually. The experiments performed usingtheoxide mixtures CaO-WO₃and MnO-TiO₂(which have lower viscosity compared to that ofCaO-B₂O₃and a ceramic material structure) showed betterpool-coolant mixing and rapid quenching of the melt. Theporosity obtained was uniformly distributed throughout themelt. DECOBI program, thus, reveals that, through this schemeof coolant injection the debris arriving in the containment asa result of vessel failure can be quenched in a relativelyshort time. Analysis performed, based on the insights gainedfrom the experiments, estimates the amount of porosity that canbe obtained with a single nozzle.

Thesecond partof the thesis is focused on the issue of thelight gas effects on the efficiency of a Passive ContainmentCooling System (PCCS) for a Boiling Water Reactor. The presenceof hydrogen affects the efficiency of PCCS, sincenon-condensable gases reduce the steam condensation rate andconsequently the efficiency of the condensers. The gasdistribution not only influences the PCC performance but alsoaffects the containment pressure build-up. The data and someanalysis of a series of four system transient tests performedin the PANDA facility, show that retention of non-condensablegas in the DW could mitigate the system pressure. The PCC(Passive Cooling Condenser) operation modes are qualitativelydiscussed and the PCCS performance is analyzed for one test byquantifying the major heat sinks (PCC pools, wetwell pool, RPVwater, structural materials, etc) and comparing them during thetest period with the decay heat (heat source) generated in theRPV. The heat transfer coefficients in one PCC have beendetermined for one test at selected times before, during andafter helium injection. In this way, the effect of light gashas been quantified in term of variation of heat transferrate.

Keywords:DECOBI, nuclear severe accident, PANDA,PCCS.

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Carlsson, Johan. "Inherent Safety Features and Passive Prevention Approaches for Pb/Bi-cooled Accelerator-Driven Systems". Doctoral thesis, KTH, Physics, 2003. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-3503.

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This thesis is devoted to the investigation of passivesafety and inherent features of subcritical nucleartransmutation systems - accelerator-driven systems. The generalobjective of this research has been to improve the safetyperformance and avoid elevated coolant temperatures inworst-case scenarios like unprotected loss-of-ow accidents,loss-of-heat-sink accidents, and a combination of both theseaccident initiators. The specific topics covered are emergencydecay heat removal by reactor vessel auxiliary cooling systems,beam shut-off by a melt-rupture disc, safety aspects fromlocating heat-exchangers in the riser of a pool-type reactorsystem, and reduction of pressure resistance in the primarycircuit by employing bypass routes.

The initial part of the research was focused on reactorvessel auxiliary cooling systems. It was shown that an 80 MWthPb/Bi-cooled accelerator-driven system of 8 m height and 6 mdiameter vessel can be well cooled in the case of loss-of-owaccidents in which the accelerator proton beam is not switchedoff. After a loss-of-heat-sink accident the proton beam has tobe interrupted within 40 minutes in order to avoid fast creepof the vessel. If a melt-rupture disc is included in the wallof the beam pipe, which breaks at 150 K above the normal coreoutlet temperature, the grace period until the beam has to beshut off is increased to 6 hours. For the same vessel geometry,but an operating power of 250 MWth the structural materials canstill avoid fast creep in case the proton beam is shut offimmediately. If beam shut-off is delayed, additional coolingmethods are needed to increase the heat removal. Investigationswere made on the filling of the gap between the guard and thereactor vessel with liquid metal coolant and using water spraycooling on the guard vessel surface.

The second part of the thesis presents examinationsregarding an accelerator-driven system also cooled with Pb/Bibut with heat-exchangers located in the risers of the reactorvessel. For a pool type design, this approach has advantages inthe case of heat-exchanger tube failures, particularly if wateris used as the secondary uid. This is because a leakage ofwater from the secondary circuit into the Pb/Bi-cooled primarycircuit leads to upward sweeping of steam bubbles, which wouldcollect in the gas plenum. In the case of heatexchangers in thedowncomer steam bubbles may be dragged into the ADS core andadd reactivity. Bypass routes are employed to increase the owspeed in loss-of-ow events for this design. It is shown thatthe 200 MWth accelerator-driven system with heat-exchangers inthe riser copes reasonably well with both a loss-of-ow accidentwith the beam on and an unprotected loss-of-heat-sink accident.For a total-loss-of-power (station blackout) and an immediatebeam-stop the core outlet temperature peaks at 680 K. After acombined loss-of-ow and loss-of-heat-sink accident the beamshould be shut off within 4 minutes to avoid exceeding the ASMElevel D of 977 K, and within 8 minutes to avoid fast creep.Assuming the same core inlet temperature, both the reactordesign with heat-exchanger in the risers and the downcomershave similar temperature evolutions after a total-loss-ofpoweraccident.

A large accelerator-driven system of 800 MWth with a 17 mtall vessel may eventually become a standard size. For thishigher power ADS, the location of the heat-exchangers hasgreater impact on the natural convection capability. This isdue to that larger heatexchangers have more inuence on thedistance between the thermal centers during a lossof- owaccident. The design with heat-exchangers in the downcomers,the long-term vessel temperature peaks at 996 K during aloss-of-ow accident with the beam on. This does not pose athreat of creep rupture for the vessel. However, the locationof the heat-exchangers in the downcomers will probably requiresecondary coolant other than water, like for example oil (fortemperatures not higher than 673 K) or Pb/Bi coolant.

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Takeuchi, Yuto. "BASIC STUDIES OF CONVECTION HEAT TRANSFER RELATED TO PASSIVE SAFETY OF FAST BREEDER REACTORS". Kyoto University, 1997. http://hdl.handle.net/2433/192978.

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Mäck, Markus [Verfasser]. "A Possibilistic Multifidelity Approach for the Uncertainty Analysis of Passive Safety Structures / Markus Mäck". Düren : Shaker, 2021. http://d-nb.info/1236834372/34.

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Książki na temat "Passive safety"

Kramer, Florian. Passive Sicherheit von Kraftfahrzeugen: Biomechanik - Simulation - Sicherheit im Entwicklungsprozess. Wyd. 3. Wiesbaden: Vieweg+Teubner Verlag / GWV Fachverlage, Wiesbaden, 2009.

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Office, General Accounting. Motor vehicle safety: Passive restraints needed to make light trucks safer : report to congressional requesters. Washington, D.C: The Office, 1989.

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Natalizio, A. ITER safety task NID-5a: On the effect of tritium sorption on building surfaces as a passive mechanism for reducing airborne concentrations. Mississauga, Ont: CFFTP, 1994.

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Kramer, Florian. Quantifizierung der passiven Sicherheit. Bergisch Gladbach: Bundesanstalt für Strassenwesen, Bereich Unfallforschung, 1988.

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A desperate passion: An autobiography. New York: W.W. Norton, 1996.

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Branch, Ontario Ministry of Transportation Research and Development. Cost-effectiveness of passing lanes: Safety, level of service and cost factors. Downsview, Ont: Research and Development Branch, Ontario Ministry of Transportation, 1991.

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Khan, A. M. Cost-effectiveness of passing lanes: Safety, level of service and cost factors. Downsview, Ont: Research and Development Branch, Ontario Ministry of Transportation, 1991.

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California. Department of Transportation. The need for passing lanes on rural two-lane highways. Sacramento]: California Dept. of Transportation, 1989.

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Orsborn, John F. Culvert design flows for fish passage and structural safety in East Cascade and Blue Mountain streams. [Olympia, Wash.]: Washington State Dept. of Transportation, 2002.

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Institute of Medicine (U.S.). Committee on Creating a Vision for Space Medicine during Travel Beyond Earth Orbit. Safe passage: Astronaut care for exploration missions. Redaktorzy Ball John 1944- i Evans Charles H. 1940-. Washington, D.C: National Academy Press, 2001.

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Części książek na temat "Passive safety"

Morello, Lorenzo, Lorenzo Rosti Rossini, Giuseppe Pia i Andrea Tonoli. "Passive Safety". W Mechanical Engineering Series, 463–558. Dordrecht: Springer Netherlands, 2011. http://dx.doi.org/10.1007/978-94-007-0516-6_7.

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Lőrincz, Márton. "Passive Bilateral Teleoperation with Safety Considerations". W Human–Robot Interaction, 171–86. Boca Raton, FL : CRC Press/Taylor & Francis Group, [2019]: Chapman and Hall/CRC, 2019. http://dx.doi.org/10.1201/9781315213781-11.

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Xiong, Y., L. Xiao, Y. Liu i Y. Zhang. "Passive safety applications in high consequence systems". W Risk, Reliability and Safety: Innovating Theory and Practice, 1361–64. Taylor & Francis Group, 6000 Broken Sound Parkway NW, Suite 300, Boca Raton, FL 33487-2742: CRC Press, 2016. http://dx.doi.org/10.1201/9781315374987-203.

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Bartkowski, Piotr, i Robert Zalewski. "Designing Process of the Drone’s Passive Safety System". W New Advances in Information Systems and Technologies, 729–37. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-31307-8_74.

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Garaniya, Vikram, Jia Wui Lim, Til Baalisampang i Rouzbeh Abbassi. "Numerical Assessment of Passive Fire Protection in an Oil and Gas Storage Facility". W Advances in Industrial Safety, 1–21. Singapore: Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-6852-7_1.

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Mehta, Vatsal, R. Ujwal, Rakshith Narun, Savan Vachhani i Babu Rao Ponangi. "Passive Safety System for Two- and Four-Wheeled Vehicles". W Lecture Notes in Electrical Engineering, 173–84. Singapore: Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-2612-1_16.

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Wismans, Jac. "Models in Injury Biomechanics for Improved Passive Vehicle Safety". W Crashworthiness of Transportation Systems: Structural Impact and Occupant Protection, 221–36. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5796-4_10.

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Fainello, M. "Optimizing passive vehicle dynamics for active safety and autonomous driving". W Proceedings, 243–51. Wiesbaden: Springer Fachmedien Wiesbaden, 2017. http://dx.doi.org/10.1007/978-3-658-18459-9_17.

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Solanki, R. B., Suneet Singh, P. V. Varde i A. K. Verma. "Estimating Passive System Reliability and Integration into Probabilistic Safety Assessment". W Reliability, Safety and Hazard Assessment for Risk-Based Technologies, 3–13. Singapore: Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-9008-1_1.

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Nayak, A. K. "Design of Advanced Reactors with Passive Safety Systems: The Reliability Concerns". W Risk Based Technologies, 25–48. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-13-5796-1_3.

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Streszczenia konferencji na temat "Passive safety"

Reyes, Jose´ N. "NuScale Approach to Passive Safety". W ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57887.

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The unprecedented seismic event and tsunami that caused the prolonged power outage at the Fukushima Daiichi nuclear plant have highlighted the importance of establishing stable long term cooling of the nuclear fuel and the containment following a complete station blackout. This paper presents an overview of the advanced passive safety systems implemented in the NuScale nuclear power plant. During normal operation, each NuScale containment is fully immersed in a water-filled stainless steel lined concrete pool that resides underground. The pool, housed in a Seismic Category I building, is large enough to provide 30 days of core and containment cooling without adding additional water. After 30 days, the decay heat generation is sufficiently small that natural convection heat transfer to air on the outside surface of the containment coupled with thermal radiation heat transfer is completely adequate to remove core decay heat for an indefinite period of time. These passive safety systems can perform their function without requiring an external supply of water, power, or generators. A complete assessment of the NuScale passive safety systems is being performed through a comprehensive test program that includes the NuScale integral system test facility at Oregon State University.

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Domhan, Martin. "Guardrails and Passive Safety for Motorcyclists". W SAE International Congress and Exposition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 1987. http://dx.doi.org/10.4271/870242.

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Reyes, Jose´ N., i Eric Young. "The NuScale Advanced Passive Safety Design". W ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6658.

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NuScale Power is designing an advanced passive nuclear power plant that does not rely on any external sources of power or coolant for safety. Accordingly, the NuScale design inherently prevents the types of issues which led to fuel damage at the Fukushima Daiichi facility. This paper presents an overview of the advanced passive safety systems implemented in the NuScale nuclear power plant. During normal operation, each NuScale containment is fully immersed in a water-filled stainless steel lined concrete pool that resides underground. The pool, housed in a Seismic Category I building, is large enough to provide 30 days of core and containment cooling without adding additional water. After 30 days, the decay heat generation is sufficiently small that natural convection heat transfer to air on the outside surface of the containment coupled with thermal radiation heat transfer is completely adequate to remove core decay heat for an indefinite period of time. These passive safety systems can perform their function without requiring an external supply of water, power, or generators.

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Marque`s, M., J. F. Pignatel, F. D’Auria, L. Burgazzi, C. Mu¨ller, G. Cojazzi i V. La Lumia. "Reliability Methods for Passive Safety Functions". W 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22274.

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This paper presents the study performed within the framework of a European Project called Reliability Methods for Passive Safety Functions (RMPS). Its objective is to propose a specific methodology to assess the passive system thermal-hydraulic (T-H) reliability. The methodology is tested on an example of industrial passive system: the Isolation Condenser System (ICS). The T-H calculations are performed using the RELAP5, ATHLET and CATHARE computer codes. In this paper, the present state of the methodology and its application to the example are described. Owing to the recent start of the project, only results concerning the first objective of the project (identification and quantification of the sources of uncertainties and determination of the important variables) are presented. A sensitivity analysis was carried out on 69 computation results performed with the RELAP5 code. This first analysis highlights the significant parameters influencing the performances of the ICS and shows a non-monotonous behavior of the system.

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"MOTORCYCLE SAFETY FEATURES, CONTEMPORARY ELEMENTS OF ACTIVE AND PASSIVE SAFETY". W Transport for Today's Society. Faculty of Technical Sciences Bitola, 2019. http://dx.doi.org/10.20544/tts2018.p32.

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Kuttenberger, Alfred, Sybille Eisele, Thomas Lich, Thorsten Sohnke, Jorge Sans Sangorrin, Michael Schmid i Marc Theisen. "Improved Occupant Protection through Cooperation of Active and Passive Safety Systems – Combined Active and Passive Safety CAPS". W SAE 2006 World Congress & Exhibition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 2006. http://dx.doi.org/10.4271/2006-01-1144.

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Sato, Takashi, Makoto Akinaga, Yoshihiro Kojima, Tsunekazu Murakami i Kenji Hosomi. "Three Types of a Passive Safety Containment for a Near Future BWR With Active and Passive Safety Systems". W 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29789.

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The paper presents three types of a passive safety containment for a near future BWR. They are tentatively named Mark S+, Mark D and Mark X containments in the paper. They all have a leak tight secondary containment vessel (SCV) in order to meet the reactor site criteria without relying on an active standby gas treatment system at a DBA LOCA. One of their common features is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The containment pressure can be limited within the design pressure. Even if a large amount of hydrogen is generated at a severe accident, it can be released into the SCV. Hydrogen detonation or deflagration is completely prevented without using igniters. Another feature is the capability to submerge the PCV and the RPV above the core level without relying on accident management. The core debris is completely submerged not only ex-vessel but also in-vessel. The third feature is robustness against external events such as a large commercial airplane crash. All the containments have built-in passive safety systems (BIPSS) including a passive containment cooling system (PCCS) and a passive cooling core catcher that has radial cooling channels. The Mark S+ and Mark D containments are applicable to a large power BWR up to 1830 MWe. The SCV is made of steel-concrete composite. The PCV can be vented into the inerted part of the SCV at a severe accident. The Mark X containment has the steel secondary containment vessel (SSCV) and can be cooled by natural convection of outside air. It can accommodate a medium power BWR up to about 1000 MWe and has a permanent grace period without replenishing the PCCS pool. In all cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides in-depth protection against severe accidents and also enables N+2 design. All the three containments coupled with the IDHS can potentially provide an evacuation free plant at a severe accident caused by severe natural disasters such as a giant earthquake, a tsunami, a mega hurricane, and so on.

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Zebardast, O., H. Moradi i F. Najafi. "Safe joint mechanism using passive compliance method for collision safety". W 2013 First RSI/ISM International Conference on Robotics and Mechatronics (ICRoM 2013). IEEE, 2013. http://dx.doi.org/10.1109/icrom.2013.6510089.

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Ueda, N., I. Kinoshita, Y. Nishi, A. Minato, H. Matsumiya i Y. Nishiguchi. "Passive Safety Features in Sodium Cooled Super-Safe, Small and Simple Reactor". W 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22354.

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This paper describes the passive safety features utilized in the updated sodium cooled Super-Safe, Small and Simple fast reactor, which is the improved 4S reactor. This reactor can operate up to ten years without refueling and neutron reflector regulates the reactivity. One of the design requirements is to secure the core against all anticipated transients without reactor scram. Therefore, the reactor concept is to design to enhance the passive safety features. All temperature reactivity feedback coefficients including whole core sodium void worth are negative. Also, introducing of RVACS (Reactor Vessel Auxiliary Cooling System) can enhance the passive decay heat removal capability. Safety analyses are carried out to simulate various transient sequences, which are loss of flow events, transient overpower events and loss of heat sink events, in order to evaluate the passive safety capabilities. A calculation tool for plant dynamics analyses for fast reactors has been modified to model the 4S including the unique plant system, which are reflector control system, circulation pumps and RVACS. The analytical results predict that the designed passive features improve the safety in which temperature variation in transients are satisfied with the safety criteria for the fuel element and the structure of the primary coolant boundary.

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Mensa, Genís, Núria Parera i Alba Fornells. "Camera Alignment System for Passive Safety Crash Tests". W WCX™ 17: SAE World Congress Experience. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 2017. http://dx.doi.org/10.4271/2017-01-1675.

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Raporty organizacyjne na temat "Passive safety"

Greenspan, Ehud. Enhanced Performance Fast Reactors with Engineered Passive Safety Systems. Office of Scientific and Technical Information (OSTI), styczeń 2019. http://dx.doi.org/10.2172/1493713.

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Zhong, Zhaopeng, i Yousry Gohar. Passive Safety Features Evaluation of KIPT Neutron Source Facility. Office of Scientific and Technical Information (OSTI), czerwiec 2016. http://dx.doi.org/10.2172/1330565.

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Cahalana, J. E., i D. Hahn. Final report-passive safety optimization in liquid sodium-cooled reactors. Office of Scientific and Technical Information (OSTI), sierpień 2007. http://dx.doi.org/10.2172/929250.

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Murao, Y., F. Araya i T. Iwamura. A concept of JAERI passive safety light water reactor system (JPSR). Office of Scientific and Technical Information (OSTI), wrzesień 1995. http://dx.doi.org/10.2172/107771.

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brian G. Woods, Jr Jose Reyes, John Woods, John Groome i Richard Wright. Testing of Passive Safety System Performance for Higher Power Advanced Reactors. Office of Scientific and Technical Information (OSTI), grudzień 2004. http://dx.doi.org/10.2172/836284.

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M. Ishii, S. T. Revankar, T. Downar, H. J. Yoon Y. Xu, D. Tinkler i U. S. Rohatgi. MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS. Office of Scientific and Technical Information (OSTI), czerwiec 2003. http://dx.doi.org/10.2172/811897.

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Robert W Youngblood. Treatment of Passive Component Reliability in Risk-Informed Safety Margin Characterization FY 2010 Report. Office of Scientific and Technical Information (OSTI), wrzesień 2010. http://dx.doi.org/10.2172/1004257.

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Winters, J. W., M. M. Corletti i Y. Hayashi. Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features. Office of Scientific and Technical Information (OSTI), listopad 2003. http://dx.doi.org/10.2172/817028.

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Forsberg, C. W., i W. J. Reich. Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who. Office of Scientific and Technical Information (OSTI), wrzesień 1991. http://dx.doi.org/10.2172/6365276.

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Brereton, S. J., D. F. Holland i S. J. Piet. Development of the passive safety concept and its application to ITER (International Thermonuclear Experimental Reactor). Office of Scientific and Technical Information (OSTI), listopad 1989. http://dx.doi.org/10.2172/7264676.

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