Relevant bibliographies by topics / Containment building

Academic literature on the topic 'Containment building'

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Published: 10 December 2022
Last updated: 29 January 2023

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Journal articles on the topic "Containment building"

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Charpin, Laurent, Jessica Haelewyn, Anass Cherki El Idrissi, Julien Niepceron, Benoît Masson, Charles Toulemonde, Guillaume Boulant, et al. "Predicting leakage of the VERCORS mock-up and concrete containment buildings - a digital twin approach." Acta Polytechnica CTU Proceedings 33 (March 3, 2022): 78–84. http://dx.doi.org/10.14311/app.2022.33.0078.

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EDF operates a nuclear power generation fleet made up of 56 reactors. This fleet contains 24 reactors designed as double-walled concrete containment building. The inner concrete containment vessel has no metallic liner and is a prestressed reinforced concrete building. The inner concrete containment vessel is designed to withstand a severe accident, in terms of mechanical and sealing behaviour. The tightness of the containment is tested every 10 years, by carrying out a pressurization test and by measuring the leak rate. The leak rate is required to be below a regulatory threshold to continue operation of the concrete containment building for the next ten years. Ageing of concrete due to drying, creep and shrinkage leads to increase prestress loss and then leak rate with time. For some containment buildings, the leak rate gets closer to the regulatory threshold with time, so important coating programs are planned to mitigate and limit the leak rate under the regulatory threshold. Therefore, it is very important for EDF to have a concrete containment building leak rate prediction tool. To address this issue, an important research program around a 1/3 scale concrete containment building mock-up called "VERCORS" have been launched at EDF. The mock-up is heavily instrumented, and its materials (concrete, prestressing cables) have been widely characterized and studied. An important numerical effort has also been made to implement structural computations of the mock-up and to capitalize these computations as well as their post-processing (so as to compare automatically with the monitoring data) in what can be called a digital twin of the mock-up. This digital twin is now used to predict the leakage of VERCORS mock-up before yearly pressure test, and also to optimize the repair programs on the real containments.
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Haynes, Karmella A. "Building genetic containment." Nature Chemical Biology 12, no. 2 (January 19, 2016): 55–56. http://dx.doi.org/10.1038/nchembio.2004.

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Zheng, Zhi, Changhai Zhai, Xu Bao, and Xiaolan Pan. "Seismic capacity estimation of a reinforced concrete containment building considering bidirectional cyclic effect." Advances in Structural Engineering 22, no. 5 (October 25, 2018): 1106–20. http://dx.doi.org/10.1177/1369433218806034.

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This study serves to estimate the seismic capacity of the reinforced concrete containment building considering its bidirectional cyclic effect and variations of energy. The implementation of the capacity estimation has been performed by extending two well-known methods: nonlinear static pushover and incremental dynamic analysis. The displacement and dissipated energy demands are obtained from the static pushover analysis considering bidirectional cyclic effect. In total, 18 bidirectional earthquake intensity parameters are developed to perform the incremental dynamic analysis for the reinforced concrete containment building. Results show that the bidirectional static pushover analysis tends to decrease the capacity of the reinforced concrete containment building in comparison with unidirectional static pushover analysis. The 5% damped first-mode geometric mean spectral acceleration strongly correlates with the maximum top displacement of the containment building. The comparison of the incremental dynamic analysis and static pushover curves is employed to determine the seismic capacity of the reinforced concrete containment building. It is concluded that bidirectional static pushover and incremental dynamic analysis studies can be used in performance evaluation and capacity estimation of reinforced concrete containment buildings under bidirectional earthquake excitations.
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Ural, E. A., and F. Tamanini. "Thermal Analysis of Hydrogen Combustion in a 1/4-Scale Boiling Water Reactor Containment Building." Journal of Heat Transfer 112, no. 1 (February 1, 1990): 201–6. http://dx.doi.org/10.1115/1.2910345.

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A mathematical model has been developed for the analysis of hydrogen combustion in boiling water reactor containment buildings. The overall phenomenon is similar to that observed in enclosure fires with the major differences being: (1) The containment building is hermetically sealed, and (2) diffusion flames form above a water pool at the bottom of the containment, through which hydrogen is released. The calculated results are compared with data obtained in tests performed in a 1/4-scale model of the containment building. The zone modeling approach, which was used in these calculations, has been demonstrated to be suitable for application to the combustion dynamics produced by the hydrogen flames in containment volumes.
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Greifinger, Robert B., and Maura S. Bluestone. "Building physician alliances for cost containment." Health Care Management Review 11, no. 4 (1986): 63–72. http://dx.doi.org/10.1097/00004010-198601140-00007.

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Cooley Warren, L. "5325642 Geodesic hazardous waste containment building." Environment International 21, no. 3 (January 1995): XIII. http://dx.doi.org/10.1016/0160-4120(95)99263-2.

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Huterer, J., E. C. Ha, D. G. Brown, and P. C. Cheng. "Darlington GS vacuum building - Containment shell." Nuclear Engineering and Design 85, no. 2 (March 1985): 131–40. http://dx.doi.org/10.1016/0029-5493(85)90279-1.

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Fanous, F., and L. Greimann. "A Simplified Axisymmetric Analysis of Steel Containment Under General Dynamic Pressure." Journal of Pressure Vessel Technology 112, no. 1 (February 1, 1990): 65–70. http://dx.doi.org/10.1115/1.2928589.

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Loadings to cause severe accidents on containment buildings can include combinations of uniform internal pressure, dynamic pressure, and seismic. Most studies that have been conducted to predict containment building capacity have focused on the effect of over pressurization on containment performance. A simple methodology that permits rapid and reasonably accurate analysis for assessing the capacity of steel containment buildings; due to global or local uniform or spatially varying dynamic loading was developed. An axisymmetric model was used and the circumferential variation of the pressure, displacements, and stress resultants were represented by Fourier series. Shell vibration and buckling analysis were performed using modified versions of BOSOR4 and BOSOR5 finite difference codes. The modified version of BOSOR5 allows the input of pressures that vary along the meridional direction. These pressures were increased until failure of the containment occurred. Failure was defined to occur when membrane strains reached twice the yield strain or the bifurcation point was introduced. The axisymmetric analysis demonstrated a powerful tool to access the capacity of steel containment buildings.
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Wang, Xiaoxin, Qin Zhou, Li Shi, Haitao Wang, and Xiaotian Li. "An Integral Numerical Analysis of Impact of a Commercial Aircraft on Nuclear Containment." Science and Technology of Nuclear Installations 2019 (October 13, 2019): 1–15. http://dx.doi.org/10.1155/2019/9417954.

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After the September 11 attack, the resistant capability of containments against aircraft impacts is required to be assessed for newly constructed nuclear power plants (NPPs). In this paper, the crash of a commercial airplane Boeing 767-200ER on the reinforced concrete containment building of an NPP is analyzed using the missile-target interaction method. Two plane models with the same total weight but different fuel distribution are analyzed. The force-time history obtained by FEA (finite element analysis) is compared with the one calculated by the Riera function. In the integral analysis, the mesh sensitivity of the reinforced concrete containment model is studied, and recommendations are provided on the modelling of containment. The impact phenomenon and damage on the containment are investigated through the validated model. The fuel distribution in the aircraft is found to have strong influence on the damage of the containment, which indicates that the load distribution in the transverse direction is critical in the analysis of aircraft impact. The classic load-time function analysis is unable to incorporate this factor and may not be adequate to provide satisfactory results. For this reason, the application of an integral analysis is advantageous in the safety assessment of aircraft impact.
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Zhou, Guo Liang, and Hui Tang. "Modal Analysis and Seismic Response Evaluation on Structures of Advanced PWR." Advanced Materials Research 838-841 (November 2013): 1471–75. http://dx.doi.org/10.4028/www.scientific.net/amr.838-841.1471.

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To evaluate the earthquake resistant behavior of the nuclear island buildings of new generation PWR, in this study we formed the three dimensional finite element model of nuclear island structures ,which incluse shield building, the auxiliary building, the containment vessel, and the containment internal structures. Modal analysis was performed to to reveal the structural dynamic characteristics.And with the auumption of hard bedrock support media ,the dynamic response nanalysis of the nuclear structures under earthquake was conducted,respectively with response spectrum method and time history method.It shows that the seimic response of the strucures conform with the design level.Under the input excitations of SSE(safe shutdown earthquake) level, the iner forces and deforamtions can be well controlled in linear elasticity.
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Dissertations / Theses on the topic "Containment building"

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Pauli, Lisa M. "Containment building : architecture between the city and advanced nuclear reactors." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/62885.

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Thesis (M. Arch.)--Massachusetts Institute of Technology, Dept. of Architecture, 2011.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Page 127 blank Cataloged from student submitted PDF version of thesis.
Includes bibliographical references (p. 124-126).
Since the inception of nuclear energy research, the element thorium (Th) has been considered the superior fuel for nuclear reactions because of its potency, safety, abundance and reduced waste. Cold War agendas broke from the logic of efficient energy production to establish a nationwide network of reactors designed to enrich uranium fuel for a nuclear arsenal. Contemporary dilemmas of global warming, increasing fuel prices, carbon emissions, and anti-proliferation movements have brought the discussion of clean, safe nuclear power to the forefront of American energy policy; it is no longer tolerable or sustainable to rely on a uranium (U) nuclear network. The architectural typology of nuclear energy has not been addressed in America for 35 years and is one that belies the promise of clean energy's progress through technology and public intervention. Containment Building is an architectural response to nuclear technological advancement that challenges historical separation between nuclear power and the public. It is a self-sustained, thorium-powered nuclear plant sited in and powering New York City. It is a nuclear campus that programatically and urbanistically engages the public and contains radio isotope labs, a nuclear medicine and imaging facility, a food irradiation center, a wellness hotel and spa, an electric taxi charging station, and a plug-in park along the Hudson River waterfront.
by Lisa M. Pauli.
M.Arch.
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SILVEIRA, RENATO C. da. "Avaliacao da estabilidade estrutural de contencoes metalicas de centrais nucleares." reponame:Repositório Institucional do IPEN, 2000. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10795.

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Made available in DSpace on 2014-10-09T12:44:06Z (GMT). No. of bitstreams: 0
Made available in DSpace on 2014-10-09T14:07:42Z (GMT). No. of bitstreams: 1 06918.pdf: 6007370 bytes, checksum: f6ef6e6f5a008b13818a5ead0efc8237 (MD5)
Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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Könönen, Mattias. "Temperature induced stresses in a reactor containment building : A case study of Forsmark F1." Thesis, KTH, Betongbyggnad, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-100834.

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Målen med denna uppsats var att studera två aspekter av temperatur inducerade spänningar med referens till kärnkraftsanläggningen Forsmark F1. Ena aspekten inkluderade den termiska kyleffekten av de ventilerade spännkabelrören i cylinderväggen. Det var av intresse att studera om den termiska kyleffekten av de ventilerade spännkabelrören hade en positiv global effekt som var relevant att beakta i globala tredimensionella modeller. Den andra aspekten inkluderade inverkan av ingjutet stål i den övreringplattan. Med syftet att studera om ingjutet stål var en aspekt som ansågs nödvändigt att beakta i transienta analyser.   Huvudanalyseringsverktyg var finita element metoden (FEM), genom användning av det kommersiellt tillgängliga finita element programmet SOLVIA.   Inverkan av den termiska kyleffekten av de ventilerade spännkabelrören indikerade en spännings reducerande effekt, med reducerade zoner av sprucken betong i cylinderväggen vid förhöjda temperaturer. Inverkan av ingjutet stål indikerade ökade temperaturskillnader mellan det ingjutna stålet och den omgivande betongen, med sprucken betong lokalt mellan stålet och betongen vid förhöjda temperaturer. Den termiska kyleffekten av de ventilerade spännkabelrören ansågs relevant att beakta i globala tredimensionella modeller. Ingjutet stål ansågs vara nödvändigt att inkludera i transienta analyser.
The aims of this thesis were to study two aspects of temperature induced stresses with reference to the nuclear power plant Forsmark F1. One aspect included the thermal cooling effect of the ventilated tendon ducts in the cylinder wall. It was of interest to study if the thermal cooling effect of the ventilated tendon ducts had a positive global effect which was relevant to consider in global three-dimensional models. The other aspect included the influence of embedded steel in the upper ring slab. With the purpose to study if embedded steel was an aspect that was considered necessary to include in transient analyses.   The used main analysis tool was the finite element method (FEM), through the use of the commercially available finite element program SOLVIA.   The influence of the thermal cooling effect of the ventilated tendon ducts indicated a stress reducing effect, with reduced cracked concrete in the cylinder wall at elevated temperatures. The influence of embedded steel indicated increased temperature differences between the embedded steel and the surrounding concrete, with cracked concrete locally between the steel and the concrete at elevated temperatures. The thermal cooling effect of the ventilated tendon ducts was considered relevant to consider in global three-dimensional models. Embedded steel was considered necessary to include in transient analyses.
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Jacobs, Louis Egbert. "A conceptual study of a natural circulation cooling loop for a PWR containment / Jacobs L.E." Thesis, North-West University, 2011. http://hdl.handle.net/10394/7608.

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The removal of heat from the containment building is an important consideration in the design of a nuclear power plant. In this investigation a simple rectangular natural circulation loop was simulated to determine whether it could possibly be used to remove usable quantities of heat from a containment building. The loop had a vertical pipe on the inside and outside of the containment building. These pipes acted as heat exchangers. Single phase and two phase cases were simulated by imposing a temperature on the respective vertical leg pipe walls and determining the heat absorption from the containment building. The heat was conveyed from the inside of the building to the outside via the natural circulation phenomenon. A literature study was done to cover topics relevant to this investigation. A theoretical model using conservation equations and control volumes was derived. This model was based largely on knowledge gleaned from the literature study. The theoretical model was a simple homogenous model, which was sufficiently detailed for a conceptual investigation. The theoretical model was then manipulated into a form suitable for use in a computer simulation program. Simplifications were made to the simulation model and underlying theory due to the nature of the investigation. The simulation model was validated against published experimental results. During the simulation phase a number of cases were investigated. These cases were divided into base cases and parametric studies. During the base case simulations the change of key fluid variables along the loop was examined. During the parametric studies the hot and cold leg inside wall temperatures, loop geometry and pipe diameter were varied. The effect of these parameters on the heat absorption from the containment was determined. The simulations showed that with the current assumptions about 75 to 120 of the natural circulation loops are needed depending on their geometry and containment conditions. The heat removal rates that were calculated varied from 50 kW to 600 kW for a single loop. As explained in the final chapter, there are many factors that influence the results obtained. The natural circulation concept was deemed to be able to remove usable quantities of heat from the containment building.
Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.
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Seitz, Thomas Richard. "Towards 'a tolerable state of order, without war' : U.S. foreign aid, 'nation-building', and containment in Southeast Asia, 1953-1968." Thesis, University of Cambridge, 1997. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.627181.

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Edwall, Bill. "Virtual Power Plant Optimization Utilizing the FCR-N Market : A revenue maximization modelling study based on building components and a Battery Energy Storage System. Based on values from Sweden's first virtual power plant, Väla." Thesis, KTH, Skolan för industriell teknik och management (ITM), 2020. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-279520.

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Renewable energy resources are projected to claim a larger part of the Swedish power mix in coming years. This could potentially increase frequency fluctuations in the power grid due to the intermittency of renewable power generating resources. These fluctuations can in turn cause issues in the power grid if left unchecked. In order to resolve these issues, countermeasures are employed. One such countermeasure is for private actors to regulate power; in exchange they are financially compensated through reserve markets. The reserve market studied in this thesis is called Frequency Containment Reserve – Normal (FCR-N). Currently hydroelectric power provides almost all regulated power within this market. As the need for power regulation is expected to increase in the coming years, there exists a need to study other technologies capable of power regulation. This thesis focuses on one such technology called, virtual power plants. While virtual power plants are operating in other parts of the world, there were no virtual power plants operating in Sweden. As a result, the nature of an optimized virtual power plant and the economic benefits of optimization had not been previously investigated. To answer such questions, this thesis modelled and optimized the revenue of a virtual power plant. The examined virtual power plant consisted of cooling chillers, lighting, ventilation fans and a battery energy storage system. Where varying their total power demand allowed for them to provide power regulation. With the virtual power plant market in Sweden being in its infancy, this thesis serves as a first look into how an optimized virtual power plant using these components could function. To put the economic results of the optimization into context, a comparative model was constructed. The comparative model was based on a semi-static linear model. This is what the thesis’s industry partner Siemens currently uses. For the simulated scenarios, the optimized model generated at least 85% higher net revenues than the semi-static linear model. The increase in revenue holds potential to increase the uptake of virtual power plants on the Swedish market, thus increasing stability in the power grid and easing the transition to renewable energy.
Då förnyelsebara energiresurser antas omfatta en större roll av den svenska elproduktionen inom kommande år, så kan detta leda till att frekvensfluktueringar i elnätet ökar. Detta sker på grund av att den oregelbundna elproduktionen från förnyelsebara energiresurser inte matchas med konsumtion. Om dessa fluktueringar inte hanteras kan det i sin tur leda till skadliga störningar inom elnätet. För att motverka detta och således stabilisera elnätet används diverse lösningar. Ett sätt att åstadkomma ökad stabilisering i elnätet är att låta privata aktörer kraftreglera. De privata aktörerna som står för kraftregleringen gör detta i utbyte mot ekonomisk kompensation, genom att delta i reservmarknader. Den reservmarknad som studerades inom detta examensarbete kallas Frequency Containment Reserve – Normal (FCR-N). I nuläget står vattenkraft för nästan all reglerad kraft inom den här marknaden. Men då behovet av kraftreglering antas öka inom kommande år så behövs nya teknologier studeras som kan bistå med kraftregleringen. Den studerade teknologin inom detta examensarbete var ett virtuellt kraftverk. Då inga virtuella kraftverk var i bruk i Sverige då denna uppsats skrevs fanns det osäkerheter kring hur man optimalt styr ett virtuellt kraftverk och de ekonomiska fördelarna som detta skulle kunna leda till. Detta examensarbete modellerade och optimerade ett virtuellt kraftverk ur ett vinstperspektiv. Det virtuella kraftverket var uppbyggt utav kylmaskiner, ljus, ventilationsfläktar och ett batterisystem. Deras kraftkonsumtion styrdes på ett sådant sätt som lätt de bidra till kraftreglering på reservmarknaden. För att kunna analysera de ekonomiska resultaten från det optimerade virtuella kraftverket, så byggdes en jämförelsemodell. Denna jämförelsemodell är baserad på en semistatisk linjär modell, vilket är det som examensarbetets industripartner Siemens använder. Den ekonomiska jämförelsens resultat påvisade att inkomsten från den optimerade modellen var minst 85% högre än den semistatiskt linjära modellen, inom de studerade scenarierna. Denna inkomstökning skulle potentiellt kunna öka användningen av virtuella kraftverk på den svenska reservmarknaden vilket i sin tur skulle medföra högre stabilitet på elnätet. Genom att öka stabiliteten på elnätet kan således förnyelsebara energiresurser i sin tur lättare implementeras.
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Dolphyn, Bradley P. "Laminar cracking in post-tensioned concrete nuclear containment buildings." Diss., Georgia Institute of Technology, 2016. http://hdl.handle.net/1853/55017.

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As a critical public safety-related structure, the long-term integrity of post-tensioned concrete containment buildings (PCCs) is necessary for continued operation of the reactors they house. In 2009, during preparations for a steam generator replacement, extensive subsurface laminar cracking was identified in a portion of the Crystal River 3 (CR3) PCC in Florida, and the plant was permanently shut down in 2013. This study investigates potential contributing factors to the identified cracking with particular focus on the effects of high early-age temperatures on the cracking risk of the concrete, on the development of the concrete properties, and on the late-age structural behavior of the concrete. Two planar, full-scale mock-ups of a portion of the CR3 PCC were constructed and instrumented with temperature and strain gauges to monitor the thermal and mechanical behavior during representative concrete curing and post-tensioning loading. Standard- and match-cured concrete specimens were tested for determination of the time- and temperature-dependent development of thermal and mechanical concrete properties, and hydration parameters were determined for the mock-up cement paste for modeling the heat generation in the concrete. These properties and parameters were utilized in 3D finite element analysis of the mock-ups in COMSOL Multiphysics and compared with experimental results. Non-destructive evaluation via shear wave tomography was conducted on the mock-ups to identify flaws and determine the effectiveness of the methods for identifying delaminations between post-tensioning ducts approximately 10 inches beneath the concrete surface. Though early-age thermal stresses were determined not to have caused cracking in the mock-ups, the high early-age concrete temperatures resulted in decreased late-age mechanical properties that were shown to contribute to greater concrete cracking risk when the mock-up was post-tensioned. Tensile stresses exceeding the tensile strength of the concrete were identified along the post-tensioning ducts when biaxial post-tensioning loads were applied in finite element analysis, but the stresses decreased rapidly with increased distance from the ducts. Through parametric modeling, increasing the tensile strength of the concrete was identified as an effective means of reducing the cracking risk in PCCs. Additionally, relationships between the mechanical properties for the standard- and match-cured specimens were identified that could enable prediction of in-place or match-cured concrete properties based only on the results of tests on fog-cured specimens.
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Albana, Mahmoud Omar A. A. "Finite element modelling of cracking in nuclear reactor concrete containment buildings." Thesis, University of Leicester, 1991. http://hdl.handle.net/2381/34736.

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Containment buildings are required to protect the public from the effect of radioactivity released by an accident to the nuclear power plant. they must be designed to minimize leakage through cracks in building wall and so methods are needed which can predict the geometry of the cracks including their widths. This study provides a realistic model of bond action between deformed reinforcing bar and concrete which uses interface element based on measured bond characteristics combined with radial constraints to simulate wedging action. It is shown to be capable of accurately predicting stress, strain, and crack geometry in typical reinforced concrete components for a variety of loading conditions. Of particular note is the ability of the model to simulate the deterioration in bond brought about by prior application of cyclic load of high amplitude. Similitude requirements for physical models of reinforced concrete structures are examined in the light of available experimental results and predicted values. The need to correctly scale the fracture energy to ensure proper representation of the bond characteristics is demonstrated. The study ends with an examination of the suitability of higher order elements which adopt a softening characteristic to represent the effect of a primary crack and its use in analysis of a typical nuclear reactor containment building.
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Chan-JungKang and 康展榮. "Standard Operating Procedures for Structural Health Monitoring and Diagnosis of Containment Building in nuclear power plant." Thesis, 2019. http://ndltd.ncl.edu.tw/handle/qjtda3.

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Anant, Joshi Amrut. "Static and Dynamic Behavior of Reinforced Masonry : Experimental and Analytical Investigations." Thesis, 2015. http://etd.iisc.ernet.in/2005/3838.

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The most common form of dwellings in rural and semi-urban areas of India and other developing countries around the globe are one/two storey unreinforced masonry (URM) buildings. It is well known that such masonry buildings are most vulnerable during earthquakes. Out-of-plane flexural failures of walls are primarily responsible for collapse of URM buildings during an earthquake. The seismic performance of such buildings can be improved by reinforcing masonry walls in the horizontal and vertical directions with materials like steel, bamboo or fiber reinforced polymers (FRP). It is fairly easy to reinforce masonry in the horizontal direction by embedding the reinforcement in the bed joints of masonry construction. However, in the vertical direction, the reinforcement is generally provided in the cavities of hollow masonry units, which are grouted after placing the reinforcement. Even though the in-plane performance of masonry walls is enhanced with such a reinforcing technique, it still falls short in resisting out-of-plane lateral loads, as the vertical reinforcement is located close to neutral axis of bending. Hence, a novel technique of reinforcing masonry in the vertical direction on both the faces of the wall called containment reinforcement is proposed recently. Containment reinforcement improves ductility, energy dissipation and prevents overturning failure due to out-of-plane loading. The present study examines the role of containment reinforcement in improving out-of-plane / in-plane behavior of masonry. The research program consisted of characterizing the physical properties of the constituent materials of reinforced masonry, namely stabilized earth blocks, cement-soil-sand (1:1:6) mortar and steel and FRP reinforcement. The strength and elastic properties of masonry assemblages under compression, flexure and shear have been determined. The flexural behavior of three types of reinforced masonry assemblages namely; stretcher bond, English bond and rat-trap bond masonry beams under monotonic and reversed cyclic loading test protocols have been examined. The beams were reinforced with steel, Glass FRP (GFRP) and Carbon FRP (CFRP) materials. In the monotonic test protocol the moment-curvature relationships and ductility for each type of masonry beams were obtained. In the cyclic test protocols, the hysteretic behavior, energy dissipation and equivalent viscous damping characteristics were obtained. The shear behavior of unreinforced and reinforced masonry panels under diagonal tension (shear) was examined through monotonic and cyclic loading test protocols. A simple and cost effective device for producing horizontal to and fro motion to imitate earthquake ground motions, called shock table test facility, has been designed. The table platform is mounted on four wheels and moves on rails. The table is put into the motion through pendulum impacts. The table motion characteristics have been obtained using the parameters used to describe the earthquake ground motions like amplitude, frequency content, duration of the motion and mixed parameters. The parameters of the shock table motion have been compared with few of the recorded earthquake ground motions to evaluate the effectiveness of shock table testing protocol for examining the dynamic performance of scaled masonry building models. The performance of two half scaled containment reinforced masonry building models subjected to base motions provided through shock table and conventional shaking table was evaluated. The dynamic properties of masonry, responses and failure patterns were obtained. A non-linear finite element (FE) model was developed and calibrated using the experimental data generated in the flexural and shear testing of reinforced and unreinforced masonry beams and panels. The FE model was further used for analysis of half scale masonry building model tested on shock table and recalibrated by comparing responses of numerical model with experimentally measured responses. Furthermore, the finite element model was used to assess the performance of two storey unreinforced and containment reinforced symmetric/asymmetric masonry buildings subjected to a series of earthquake ground motions of increasing severity. The studies conducted conclude that the masonry with containment reinforcement was effective in mitigating seismic risks of masonry buildings in moderate to severe seismic regions. The provision of containment reinforcement significantly improved equivalent hysteretic damping at design displacement and offered excellent ductility to masonry elements. The existing construction practice can easily accommodate the provision of containment reinforcement with little modification to the construction sequence. The extra effort in construction does commensurate with the enhancement in the seismic performance of the masonry buildings.
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Books on the topic "Containment building"

1

Miller, J. D. Analysis of shell-rupture failure due to hypothetical elevated-temperature pressurization of the Sequoyah Unit 1 steel containment building. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

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Miller, J. D. Analysis of shell-rupture failure due to hypothetical elevated-temperature pressurization of the Sequoyah Unit 1 steel containment building. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

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3

Turner, Margery Austin. Building housing for the low-income elderly: Cost containment and modest design in the Section 202 program. Washington, D.C: Urban Institute, 1985.

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Brinson, D. A. Evaluation of seals for mechanical penetrations of containment buildings. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

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Brinson, D. A. Evaluation of seals for mechanical penetrations of containment buildings. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

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Aruti︠u︡ni︠a︡n, R. V. Mekhanika prednapri︠a︡zhennykh zashchitnykh obolochek AĖS. Moskva: Nauka, 2008.

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Aruti︠u︡ni︠a︡n, R. V. Mekhanika prednapri︠a︡zhennykh zashchitnykh obolochek AĖS. Moskva: Nauka, 2008.

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Fermandjian, Jean. Comparison of European computer codes relative to the aerosol behavior in PWR containment buildings during severecore damage accidents. Luxembourg: Commission of the European Communities, 1987.

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Michigan. Office of the Auditor General. Audit report: Performance audit of selected Medicaid prescription drug cost containment practices, Department of Social Services, January 1, 1991 through April 30, 1994. [Lansing, Mich.]: The Office, 1994.

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U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and Sandia National Laboratories, eds. Posttest analysis of a 1:6-scale reinforced concrete reactor containment building. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

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Book chapters on the topic "Containment building"

1

Kugeler, Kurt, and Zuoyi Zhang. "Reactor Containment Building." In Modular High-temperature Gas-cooled Reactor Power Plant, 331–46. Berlin, Heidelberg: Springer Berlin Heidelberg, 2018. http://dx.doi.org/10.1007/978-3-662-57712-7_7.

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Marcuzzi, Stefano. "From state-building to containment." In The EU, NATO and the Libya Conflict, 142–60. London: Routledge, 2021. http://dx.doi.org/10.4324/9781003091271-9.

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Masterson, Robert E. "Response of a Containment Building to a Reactor LOCA." In Nuclear Reactor Thermal Hydraulics, 1251–87. Boca Raton : CRC Press, [2019]: CRC Press, 2019. http://dx.doi.org/10.1201/b22067-34.

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Charpin, Laurent, Charles Toulemonde, Jean-Luc Adia, Florian Escoffier, Sylvie Michel-Ponnelle, Guillaume Boulant, Benoît Masson, and Julien Niepceron. "Double Wall Containment Building Leak-Tightness Prediction: Strategy and Application." In RILEM Bookseries, 227–38. Cham: Springer International Publishing, 2021. http://dx.doi.org/10.1007/978-3-030-72921-9_19.

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Gaysina, A. A., and B. K. Pergamenshchik. "Technology of Construction of the Outer Containment of Nuclear Power Plants with VVER Reactors." In Building Life-cycle Management. Information Systems and Technologies, 357–64. Cham: Springer International Publishing, 2022. http://dx.doi.org/10.1007/978-3-030-96206-7_37.

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Patel, Jigar V., Kaustubh Gadgil, C. Sengupta, and P. Sumanth. "Performance Enhancement of Reactor Building Containment Isolation System by Use of Direct-Acting Solenoid Valves." In Reliability, Safety and Hazard Assessment for Risk-Based Technologies, 671–85. Singapore: Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-9008-1_57.

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Bangash, M. Y. H. "A Complete Manual Design Analysis of Concrete Containment Vessel (Building) Using American Practices and Codes." In Structures for Nuclear Facilities, 337–449. Berlin, Heidelberg: Springer Berlin Heidelberg, 2010. http://dx.doi.org/10.1007/978-3-642-12560-7_6.

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Soueid, Ahmad, E. Clayton Teague, and James Murday. "Bio-containment." In Buildings for Advanced Technology, 121–27. Cham: Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-24892-9_10.

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Briffaut, M., M. Ghannoum, J. Baroth, H. Cheikh Sleiman, and F. Dufour. "Probabilistic Modelling of Containment Building Leakage at the Structural Scale: Application to the PACE Mock-Up." In RILEM Bookseries, 69–78. Cham: Springer International Publishing, 2022. http://dx.doi.org/10.1007/978-3-031-07746-3_7.

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Nielsen, Fran, Polly Kwan, and Nina Mather. "Group Therapies." In Longer-Term Psychiatric Inpatient Care for Adolescents, 77–84. Singapore: Springer Nature Singapore, 2022. http://dx.doi.org/10.1007/978-981-19-1950-3_9.

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AbstractThe group therapy programme at the Walker Unit uses a multimodal approach including verbal, non-verbal, and physical elements. The programme draws on expertise from a range of professional disciplines. The group programme provides therapeutic clinical intervention rather than activity or distraction-based programmes, providing structure and containment as well as cultivating engagement in the therapeutic process and therapy skill building, navigating interpersonal dynamics. Being in a contained unit, the spaces on the ward are also used to facilitate a therapeutic environment during groups. Toward the end of the admissions adolescents and their families may adopt a similarly structured programme or routine including skills and strategies, to assist with their transition from hospital and maintain therapeutic gains achieved from their admission.
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Conference papers on the topic "Containment building"

1

Koch, T., J. McEntire, P. Murray, and M. Smith. "Sodium Cooled Reactor Containment Building Footprint Optimization." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t30807.

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Park, Kweonha. "Hydrogen Distribution and Explosion in Containment Building." In The 4th World Congress on Mechanical, Chemical, and Material Engineering. Avestia Publishing, 2018. http://dx.doi.org/10.11159/htff18.143.

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Sun, Zhiyou, and Hongwei Shen. "Ventilation Management for the AP1000 Containment Building During Construction Stage." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16864.

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Confined space can be defined as closed or semi-closed equipments, facilities and places which potentially have poor ventilation, poisonous and hazardous gases or poor oxygen. Confined space has complex working environment and more hazardous factors which makes safety accidents occurred frequently. Modularized Construction, as the typical feature of AP1000 nuclear project construction, shortens the construction schedule but increases safety risk, since there is more confined space and cross work, especially in the Containment building after the setting of CVTH. This thesis analyses the confined space construction feature of the containment building and emphasizes the necessity of ventilation and fume control. Some ventilation methods have been taken on site which has effectively reduced the construction risk inside containment buildings. Therefore, this thesis has practical value for the consequent AP1000 project construction.
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Rešetar, Iva, and Norbert Palz. "Experimental Investigation of the Impact of PCM Containment on Indoor Temperature Variations." In 7th International Building Physics Conference. Syracuse, New York: International Association of Building Physics (IABP), 2018. http://dx.doi.org/10.14305/ibpc.2018.ps18.

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Xie, Jianghong. "Research on Negative Pressure Control Technology in NPP Reactor Building and its Application." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16282.

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The paper mainly elaborates the negative pressure control technology and commissioning approaches for double-wall containment of Russian WWER-1000 nuclear power units. It also carries out an analysis and research on the layered negative pressure technology in the containment. It mainly includes the following three parts: A Russian WWER-1000 nuclear power unit adopts the structure of double-wall containment for its Reactor building, with independent negative pressure systems for the containment and the annular space between the two walls. The paper mainly elaborates the control methods and limits requirements for the negative pressure in the containment and the annular space under the normal operation condition and in case of design basis accidents, with analysis and argumentation on the design function and operation requirements of the negative pressure system for the containment and the annular space. In the paper, the design philosophy of layered negative pressure and its feasibility study are analyzed from the aspects of radiated partition, air distribution of the negative pressure system and containment separator for layered negative pressure. The commissioning methods and technical requirements of negative pressure system in the Reactor building are described in the paper. Problems encountered during commissioning are also addressed and analyzed. Operations practices prove that the negative pressure control technology for double-wall containment of WWER-1000 nuclear power unit is advanced and reliable, which meets the requirements on nuclear air decontamination emission and radiation protection, and is worthy of study, research and reference.
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Jensen, P. A., and M. P. Schafer. "395. Physical and Biological Test Methods to Evaluate the Containment of Bioaerosols Within an Aerosol Chamber." In AIHce 1997 - Taking Responsibility...Building Tomorrow's Profession Papers. AIHA, 1999. http://dx.doi.org/10.3320/1.2765539.

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Dang, Junjie, Daogang Lu, Wenhui Ma, Yu Liu, and Yang Hong. "The Research of the Fluid-Solid Interaction of the Passive Containment Cooling Tank and Shield Building Structure With Seismic Load in AP1000." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15778.

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The passive containment cooling system is the ultimate heat trap and the key to ensure the safe operation of the AP1000 nuclear power plant. It is very important to keep the reliability of the passive containment cooling system (PCS) in the normal conditions and also in the abnormal conditions, especially in earthquakes. Analysis on the fluid-structure interacted characteristics of the passive containment cooling water storage tanks and shield building structure in earthquake is crucial to the assessment of the effectiveness of the PCS. According to the passive containment cooling water storage tanks and shield building structure prototype size, an experiment model was established to analyze the fluid-structure interacted characteristics of the passive containment cooling water tanks and shield building by the numerical method.
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Jiménez, Gonzalo, Rafael Bocanegra, Kevin Fernández, César Queral, and Javier Montero-Mayorga. "Development of a PWR-W and an AP1000® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30445.

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The simulation of design basis accidents in a containment building is usually conducted with a lumped parameter model. The codes normally used by Westinghouse Electric Company (WEC) for that license analysis are WGOTHIC or COCO, which are suitable to provide an adequate estimation of the overall peak temperature and pressure of the containment. However, for the detailed study of the thermal-hydraulic behavior in every room and compartment of the containment building, it could be more convenient to model the containment with a more detailed 3D representation of the geometry of the whole building. The main objective of this project is to obtain a standard PWR Westinghouse as well as an AP1000® containment model for a CFD code to analyze the thermal-hydraulic detailed behavior during a design basis accident. In this paper the development and testing of both containment models is presented.
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Kim, Seung-Huyn, Yoon-Suk Chang, Sungchu Song, and Yong-Jin Cho. "Structural Assessment of Main Steam Line and Containment Building Under Steam Explosion Conditions." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-45169.

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The steam explosion is a fuel-coolant interaction process where the heat transfer from the melt to water is quite intense and rapid. This phenomenon may threat integrity of nuclear components and structures. For instance, the dynamic loads on the reactor cavity and the reactor lower plenum could potentially lead to failure of the main steam lines connected to the steam generators. In addition, since the main steam line extends to the containment wall, failure of the containment building may occur. The object of present study is to examine characteristics of Main Steam Line (MSL) and containment building under the steam explosion conditions. In this context, the corresponding FE models were generated and previously determined displacements of penetration piping were used as loading conditions. Subsequent FE analyses were conducted for the main steam line and containment building to calculate stresses and crack evaluations. Finally, structural assessment of nuclear component and structure combined with concrete failure criteria was performed and their results were discussed.
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Takahashi, M., T. Maruyama, H. Mori, K. Hoshino, Y. Hijioka, H. Heki, M. Nakamaru, and T. Hoshi. "Advanced Construction of Compact Containment BWR." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89700.

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The reactor concept considered in this paper has a mid/small power output, a compact containment and a simplified BWR configuration with comprehensive safety features. Compact Containment BWR (CCR) is being developed with matured BWR technologies together with innovative systems/components, will provide attractiveness for the energy market in the world due to its flexibility in energy demands as well as in site conditions, its high potential in reducing investment risk and its safety feature facilitating public acceptance. The flexibility is achieved by CCR’s mid/small power output of 400 MWe class and capability of long operating cycle (refueling intervals). The high investment potential is expected from CCR’s simplification/innovation in design such as natural circulation core cooling with the bottom located short core, top mounted upper entry control rod drives (CRDs) with ring-type dryers and simplified safety system with high pressure resistible primary containment vessel (PCV) concept. The natural circulation core eliminates recirculation pumps as well as needs for maintenance of such pumps. The top mounted upper entry CRDs enable the bottom located short core in RPV. The safety feature mainly consists of large water inventory above the core without large penetration below the top of the core, passive cooling system by isolation condenser (IC), high pressure resistible PCV and in-vessel retention (IVR) capability. The large inventory increases the system response time in case of design base accidents including loss of coolant accidents. The IC suppresses PCV pressure by steam condensation without any AC power. Cooling the molten core inside the RPV if the core should be damaged by loss of core coolability could attain the IVR. CCR’s specific self-standing steel high pressure resistible PCV is designed to contain minimum piping and valves inside with reactor pressure vessel (RPV), only 13m in diameter and 24m in height. This compact PCV makes it possible to fabricate and perform pressure-test at the factory and transport to the construction-site as a module. Basing on CCR design concept of simplification and compact, reactor building layout design has been carried out. Layout design has been performed taking into account module construction, reduced system and components and compact PCV. As a result, CCR’s reactor building, specific volume to power output value is almost equal to ABWR one. Module fabrication and construction method is promising technology from the points of construction duration shortening and construction cost reduction. Electrical equipment are piled up to multi-layer and connected and tested at the factory and transported to the construction-site in one module. Other equipment rooms and areas are also built into the various pre-fabricated module types in CCR construction. The construction of the CCR by the large module is planned to achieve only 24-month construction period from bedrock inspection to commercial operation. The CCR has possibilities of attaining both economical and safe small reactor by simplified system and compact PCV technologies with advanced construction.
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Reports on the topic "Containment building"

1

Broder, M. F. Building a secondary containment system. Office of Scientific and Technical Information (OSTI), October 1994. http://dx.doi.org/10.2172/10189839.

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Caruso, A., I. Flour, O. Simonin, and C. Cherbonnel. Detailed thermal-hydraulic computation into a containment building. Office of Scientific and Technical Information (OSTI), September 1995. http://dx.doi.org/10.2172/107791.

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Weatherby, J. Posttest analysis of a 1:6-scale reinforced concrete reactor containment building. Office of Scientific and Technical Information (OSTI), February 1990. http://dx.doi.org/10.2172/7257912.

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Murdoch, B. T. Radiological status report for the EBWR containment building. Volume 1: Summary and analysis. Office of Scientific and Technical Information (OSTI), February 1996. http://dx.doi.org/10.2172/212570.

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Spletzer, B. L., L. D. Lambert, and V. L. Bergman. Separate effects testing and analyses to investigate liner tearing of the 1:6-scale reinforced concrete containment building. Office of Scientific and Technical Information (OSTI), June 1995. http://dx.doi.org/10.2172/95192.

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Weatherby, J. R. Axisymmetric analysis of a 1:6-scale reinforced concrete containment building using a distributed cracking model for the concrete. Office of Scientific and Technical Information (OSTI), September 1987. http://dx.doi.org/10.2172/5808040.

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Mahdavian, Farnaz. Germany Country Report. University of Stavanger, February 2022. http://dx.doi.org/10.31265/usps.180.

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Germany is a parliamentary democracy (The Federal Government, 2021) with two politically independent levels of 1) Federal (Bund) and 2) State (Länder or Bundesländer), and has a highly differentiated decentralized system of Government and administration (Deutsche Gesellschaft für Internationale Zusammenarbeit, 2021). The 16 states in Germany have their own government and legislations which means the federal authority has the responsibility of formulating policy, and the states are responsible for implementation (Franzke, 2020). The Federal Government supports the states in dealing with extraordinary danger and the Federal Ministry of the Interior (BMI) supports the states' operations with technology, expertise and other services (Federal Ministry of Interior, Building and Community, 2020). Due to the decentralized system of government, the Federal Government does not have the power to impose pandemic emergency measures. In the beginning of the COVID-19 pandemic, in order to slowdown the spread of coronavirus, on 16 March 2020 the federal and state governments attempted to harmonize joint guidelines, however one month later State governments started to act more independently (Franzke & Kuhlmann, 2021). In Germany, health insurance is compulsory and more than 11% of Germany’s GDP goes into healthcare spending (Federal Statistical Office, 2021). Health related policy at the federal level is the primary responsibility of the Federal Ministry of Health. This ministry supervises institutions dealing with higher level of public health including the Federal Institute for Drugs and Medical Devices (BfArM), the Paul-Ehrlich-Institute (PEI), the Robert Koch Institute (RKI) and the Federal Centre for Health Education (Federal Ministry of Health, 2020). The first German National Pandemic Plan (NPP), published in 2005, comprises two parts. Part one, updated in 2017, provides a framework for the pandemic plans of the states and the implementation plans of the municipalities, and part two, updated in 2016, is the scientific part of the National Pandemic Plan (Robert Koch Institut, 2017). The joint Federal-State working group on pandemic planning was established in 2005. A pandemic plan for German citizens abroad was published by the German Foreign Office on its website in 2005 (Robert Koch Institut, 2017). In 2007, the federal and state Governments, under the joint leadership of the Federal Ministry of the Interior and the Federal Ministry of Health, simulated influenza pandemic exercise called LÜKEX 07, and trained cross-states and cross-department crisis management (Bundesanstalt Technisches Hilfswerk, 2007b). In 2017, within the context of the G20, Germany ran a health emergency simulation exercise with representatives from WHO and the World Bank to prepare for future pandemic events (Federal Ministry of Health et al., 2017). By the beginning of the COVID-19 pandemic, on 27 February 2020, a joint crisis team of the Federal Ministry of the Interior (BMI) and the Federal Ministry of Health (BMG) was established (Die Bundesregierung, 2020a). On 4 March 2020 RKI published a Supplement to the National Pandemic Plan for COVID-19 (Robert Koch Institut, 2020d), and on 28 March 2020, a law for the protection of the population in an epidemic situation of national scope (Infektionsschutzgesetz) came into force (Bundesgesundheitsministerium, 2020b). In the first early phase of the COVID-19 pandemic in 2020, Germany managed to slow down the speed of the outbreak but was less successful in dealing with the second phase. Coronavirus-related information and measures were communicated through various platforms including TV, radio, press conferences, federal and state government official homepages, social media and applications. In mid-March 2020, the federal and state governments implemented extensive measures nationwide for pandemic containment. Step by step, social distancing and shutdowns were enforced by all Federal States, involving closing schools, day-cares and kindergartens, pubs, restaurants, shops, prayer services, borders, and imposing a curfew. To support those affected financially by the pandemic, the German Government provided large economic packages (Bundesministerium der Finanzen, 2020). These measures have adopted to the COVID-19 situation and changed over the pandemic. On 22 April 2020, the clinical trial of the corona vaccine was approved by Paul Ehrlich Institute, and in late December 2020, the distribution of vaccination in Germany and all other EU countries
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