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Journal articles on the topic 'Containment building'

Author: Grafiati

Published: 10 December 2022

Last updated: 19 July 2025

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1

Charpin, Laurent, Jessica Haelewyn, Anass Cherki El Idrissi, 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

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2

Haynes, Karmella A. "Building genetic containment." Nature Chemical Biology 12, no. 2 (2016): 55–56. http://dx.doi.org/10.1038/nchembio.2004.

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3

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 (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 reinforce

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4

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 (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 be

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5

Fanous, F., and L. Greimann. "A Simplified Axisymmetric Analysis of Steel Containment Under General Dynamic Pressure." Journal of Pressure Vessel Technology 112, no. 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,

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6

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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7

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

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8

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 (1985): 131–40. http://dx.doi.org/10.1016/0029-5493(85)90279-1.

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9

Jazbinšek, Jure, Luka Štrubelj, and Ivica Bašić. "RRESPONSE OF THE KRŠKO NUCLEAR POWER PLANT COINTAINMENT TO THE LOSS OF COOLANT ACCIDENT IN COMPUTER CODE APROS 6." Journal of Energy Technology 9, no. 1 (2024): 51–61. https://doi.org/10.18690/jet.9.1.51-61.2016.

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Containment is a combination of a steel shell and concrete shield building enclosure, completely surrounding a nuclear reactor, designed to prevent the release of radioactive material in the event of an accident. The NEK (Krško Nuclear Power Plant) reactor containment building nodalization in APROS 6 computer code has been developed based on the plant’s available documents and GOTHIC nodalization. The heat structure’s data are based on USAR (Updated Safety Analyses Report) Chapter 6 passive heat structures. In all other aspects, realistic calculations based on containment geometry have been pe

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10

Sakvarelidze, Amiran. "Construction and Calculation of Vertical Profile Type Port-Containment Buildings Built from Cement-based Composite Materials." Works of Georgian Technical University, no. 3(533) (September 26, 2024): 170–81. http://dx.doi.org/10.36073/1512-0996-2024-3-170-181.

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The main constituent part of vertical profile type port-containment buildings is a vertical wall. Buildings are distinguished according to the vertical wall’s underwater structure (built from cement-based composite materials), as: 1. Mass concretes and 2. Mass-giants 1. Port containment buildings from mass concretes. In practice, these buildings utilize conventional masses weighing up to 100 tons and Cyclopean masses exceeding 400 tons. This article addresses the technological aspects associated with constructing containment buildings using conventional concrete masses and Cyclopean masses. Ke

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11

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

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12

Valentines-Álvarez, Jaume. "Spreading the atom, encapsulating politics: a story of confinement on a nuclear containment building in Barcelona." SHS Web of Conferences 136 (2022): 01003. http://dx.doi.org/10.1051/shsconf/202213601003.

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In 2005, the containment building of the first nuclear reactor in Catalonia was silently demolished in the streets of Barcelona. The destruction was the last step in the long history of invisibilization of a nuclear facility that had been inaugurated forty years before as a “radiant symbol” of the autarkic policies of General Franco's dictatorship (1939-1977). What did the containment building contain beyond radioactivity? What ideas about the atom and the nuclear dangers did it foster? This paper will focus on the history and geography of the nuclear building with the aim of exploring the int

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13

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

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14

Kim, Taeseok, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Hoichul Jung, and Sung Joong Kim. "A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident." Science and Technology of Nuclear Installations 2018 (August 6, 2018): 1–12. http://dx.doi.org/10.1155/2018/5936214.

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During a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in nuclear power plants. However, in a bypass scenario of steam generator tube rupture (SGTR), radioactive nuclides can be released to environment even if the containment is not ruptured. Thus, thorough mitigation strategies are needed to prevent such unfiltered release of the radioactive nuclides during SGTR accidents. To mitigate the consequence of the SGTR accident, this study was conducted to devise a conceptual approach of installing

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15

Mamet, J. C., and O. Moselhi. "Outline of current analysis procedure for CANDU 600 MW reactor buildings." Canadian Journal of Civil Engineering 12, no. 4 (1985): 796–804. http://dx.doi.org/10.1139/l85-093.

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Reactor buildings of 600 MW CANDU nuclear power plants consist of a prestressed concrete containment structure, cylindrical in shape with a double spherical dome, and of a reinforced concrete internal structure with heavy walls and slabs that support the nuclear reactor, the primary heat transport system, control and safety mechanisms, etc. Both structures are supported on a common circular slab.In this paper, an outline of the static and seismic response analyses performed for these buildings is presented. Several computer models and codes are used and advantage is taken of the symmetry of re

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16

Holan, Jakub, Petr Bíly, and Radek Štefan. "Study of the Underground Placement of a Reinforced Concrete Containment Building." Advances in Science and Technology 108 (July 27, 2021): 35–44. http://dx.doi.org/10.4028/www.scientific.net/ast.108.35.

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Nowadays, the safety of nuclear power plants is of increasing interest and importance. The main reasons for increased safety concerns are the recent major nuclear accident in Fukushima in 2011 and the overall tendency of environment protection. One of the possible ways of increasing the safety of nuclear power plants is the underground placement of all potentially dangerous systems under ground as the overlying soil or rock layer would act as a "earth" containment which would reduce the probability of ground level release following primary and secondary containment failure. Moreover, partial o

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17

Nguyen, Van Thai, and Ngoc Dung Kieu. "Analysis of Containment Pressure and Temperature Changes Following Loss of Coolant Accident (LOCA)." Nuclear Science and Technology 5, no. 4 (2015): 1–8. http://dx.doi.org/10.53747/jnst.v5i4.200.

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This paper present a preliminary thermal-hydraulics analysis of AP1000 containment following loss of coolant accident events such as double-end cold line break (DECLB) or main steam line break (MSLB) using MELCOR code. A break of this type will produce a rapid depressurization of the reactor pressure vessel (primary system) and release initially high pressure water into the containment followed by a much smaller release of highly superheated steam. The high pressure liquid water will flash and rapidly pressurize the containment building. The performance of passive containment cooling system fo

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18

Bonhomme, Nicolaas M. "A new direction in PWR simplification." EPJ Nuclear Sciences & Technologies 7 (2021): 2. http://dx.doi.org/10.1051/epjn/2020020.

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A new approach to PWR simplification is presented, in which a compact Reactor Coolant System (RCS) configuration is introduced, particularly suited for a power level in the range of 600 MWe. Customary PWR primary system components are eliminated to achieve this RCS simplification. For example, RCS pressure control through a “self-pressurization” mode, with core exit at saturation temperature with less than 1% steam, allows elimination of a pressurizer. Also, mechanical control rods are replaced by reactivity control using negative moderator void and temperature coefficient together with variab

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19

Seo, Dong Won, and Hyuk Chun Noh. "Aircraft Impact Analysis of Steel Fiber Reinforced Containment Building." Journal of the Computational Structural Engineering Institute of Korea 26, no. 2 (2013): 157–64. http://dx.doi.org/10.7734/coseik.2013.26.2.157.

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20

Lee, Sang-Keun, Young-Chul Song, and Sang-Hoon Han. "Biaxial behavior of plain concrete of nuclear containment building." Nuclear Engineering and Design 227, no. 2 (2004): 143–53. http://dx.doi.org/10.1016/j.nucengdes.2003.09.001.

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21

Fanous, Fouad, Lowell Greimann, and Wagdy Wassef. "Analysis of an ice-condenser containment building anchorage system." Nuclear Engineering and Design 133, no. 1 (1992): 159–68. http://dx.doi.org/10.1016/0029-5493(92)90100-a.

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22

Lugovyy, P., V. Kryts’kyi, and N. Kryts’ka. "Analysis of the Dynamic Behavior and Stress-Strain State of NPP Containment under Nonstationary Impacts." Nuclear and Radiation Safety, no. 3(71) (August 15, 2016): 38–47. http://dx.doi.org/10.32918/nrs.2016.3(71).08.

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The paper presents the analysis of dynamic behavior of the reinforced concrete containment of NPP unit under the combined effect of internal pressure shock caused by the accident in the reactor hall and seismic impact of design-basis earthquake using the finite element method (FEM) and DIPROS software. Using the modal analysis and numerical solution of the FEM equations of containment concrete, the stress-strain state of the building structure in the post-accident period was defined. It is shown that the maximum intensity of the stresses in the steel liner of the containment does not exceed th

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23

Wang, Xiaolei, and Dagang Lu. "Finite Element Reliability Analysis of Steel Containment Vessels with Corrosion Damage." Journal of Disaster Research 10, no. 3 (2015): 527–34. http://dx.doi.org/10.20965/jdr.2015.p0527.

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Containment vessels, which contain any radioactive materials that would be released from the primary system in an accident, are the last barrier between the environment and the nuclear steam supply system in nuclear power plants. Assessing the probability of failure for the containment building is essential to level 2 PSA studies of nuclear power plants. Degradation of containment vessels of some nuclear power plants has been observed in many countries, so it is important to study how the corrosion has adverse effects on the capacity of containment vessels. Conventionally, the reliability anal

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24

Fried, Jeremy S., and Burton D. Fried. "Simulating Wildfire Containment with Realistic Tactics." Forest Science 42, no. 3 (1996): 267–81. http://dx.doi.org/10.1093/forestscience/42.3.267.

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Abstract Existing simulation models for fire protection planning rely on a containment algorithm which fails to account for the interaction between the production of containment line and a fire's capacity to spread. This paper describes a technique for simulating wildland fire containment which explicitly accounts for this interaction by extending, generalizing, and, in some cases, simplifying methods reported earlier (Anderson 1983, Albini et al. 1978, Mees 1985, Anderson 1989). Representing the containment boundary in parametric form [i.e., expressing its Cartesian (x, y) or polar (r, ) coo

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25

V. Jatkar, Mohan, and Shailesh Patil. "Construction of Inner Containment Dome Reactor Building - A Case Study." IABSE Symposium Report 101, no. 6 (2013): 1–2. http://dx.doi.org/10.2749/222137813808627668.

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26

Pauli, Lisa. "Containment Building: Architecture Between the City & Advanced Nuclear Reactors." Thresholds 39 (January 2011): 92–94. http://dx.doi.org/10.1162/thld_a_00167.

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27

Varpasuo, P. "The seismic reliability of VVER-1000 NPP prestressed containment building." Nuclear Engineering and Design 160, no. 3 (1996): 387–98. http://dx.doi.org/10.1016/0029-5493(95)01116-1.

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28

Kim, Jongtae, and Kukhee Lim. "Validation and Application of a Code for Three-Dimensional Analysis of Hydrogen–Steam Behavior in a Nuclear Reactor Containment during Severe Accidents." Applied Sciences 14, no. 15 (2024): 6695. http://dx.doi.org/10.3390/app14156695.

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In a pressurized water reactor (PWR) during a loss of coolant accident (LOCA) or a station blackout (SBO) accident, water and steam are released into the containment building. The water vapor mixes with the atmosphere, partially condensing into droplets or condensing on the containment walls. Although a significant amount of water vapor condenses, it coexists with hydrogen generated by the reactor core oxidation. As water vapor condenses, the volume fraction of hydrogen increases, raising the risk of explosion or flame acceleration. As such, water vapor’s behavior directly affects hydrogen dis

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29

Yamamoto, Tomohiko, Atsushi Katoh, Yoshitaka Chikazawa, and Kazuo Negishi. "Design Evaluation Method of Steel-Plate Reinforced Concrete Structure Containment Vessel for Sodium-Cooled Fast Reactor." Journal of Disaster Research 7, no. 5 (2012): 645–55. http://dx.doi.org/10.20965/jdr.2012.p0645.

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The Japan Sodium-Cooled Fast Reactor (JSFR) adopts the new concept of a containment vessel called a steel-plate-reinforced concrete containment vessel (SCCV). The SCCV is considered to be effective in shortening construction periods by the elimination of rebar work at a site compared with applying a reinforced concrete CV. In addition to this advantage, the SCCV achieves high-quality building structure because steel structural parts are fabricated at a factory prior to site construction. Although the SC structure has been used for buildings at a light-water reactor (LWR), etc., the SC structur

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30

Santiko Tri Sulaksono, Rian Fitriana, Anwar Ilmar Ramadhan, Efrizon Umar, Sidik Permana, and Wan Hamzah Azmi. "CFD Analysis of Natural Convection on the Outer Surface of the Containment of APWR Model." Journal of Advanced Research in Fluid Mechanics and Thermal Sciences 115, no. 1 (2024): 19–29. http://dx.doi.org/10.37934/arfmts.115.1.1929.

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To improve the safety of nuclear power plants, a modern NPP such as Advance Pressurize Water Reactor (APWR) is equipped with a safety feature called PCCS (Passive Containment Cooling System), where naturally circulating air cools the outer surface of the containment which is used to remove decay heat released inside the containment vessel. The decay heat from the reactor core will be transferred out through the conduction mechanism and the natural convection mechanism on the outer surface of the containment vessel. Then, the hot air that forms in the gap between the containment and its baffles

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31

Krátký, Štěpán, and Petr Havlásek. "Benchmark VERCORS 2022: blind prediction of time-dependent behavior of concrete containment building with low and high-fidelity models." Acta Polytechnica CTU Proceedings 40 (July 24, 2023): 48–53. http://dx.doi.org/10.14311/app.2023.40.0048.

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The VERCORS program aims to acquire an extensive experimental dataset collected to provide a solid basis for numerical modeling of concrete containment buildings (CCBs). In order to cover the entire life-span of a real containment, the measurements are done on 3× smaller mock-up which leads to 9-fold acceleration of all processes related to drying. The goal for the participants of the third VERCORS benchmark was to predict the behaviour of the CCB based on standard laboratory measurements on VERCORS concrete. The previous paper [1] presented the calibration procedure of material models for moi

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32

Chavez, Maria, and Kristina Warren. "A Sound Artist’s Breakdown of Field Recording over History." Organised Sound 27, no. 1 (2022): 41–43. http://dx.doi.org/10.1017/s1355771822000218.

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The conceptual sound artist, turntablist, and curator Maria Chavez muses about storing and accessing sounds. Building on Ursula Le Guin’s concept of the carrier bag, she describes four eras of sound recording and containment.

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33

Neighbor, Noel, and David B. South. "An Evaluation of the Monolithic Dome Construction Method for Biological Containment Structures." Journal of the American Biological Safety Association 2, no. 1 (1997): 39–46. http://dx.doi.org/10.1177/109135059700200109.

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A monolithic dome was built as a residential structure using a previously developed airform technique. The building consisted of an outer airtight form, polyurethane foam insulation, and reinforced concrete. Except for the airform kit, locally available materials were used for construction using several alternatives and options applicable to this kind of building. The process and options were evaluated relative to their application for the production of biological containment facilities. It was concluded that the monolithic dome building technique is an effective alternative to conventional me

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34

Goebes, Marian D., Ellen Jo Baron, Kathleen L. Mathews, and Lynn M. Hildemann. "Effect of Building Construction on Aspergillus Concentrations in a Hospital." Infection Control & Hospital Epidemiology 29, no. 5 (2008): 462–64. http://dx.doi.org/10.1086/587189.

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Air samples taken in a hospital undergoing construction and analyzed with a quantitative polymerase chain reaction (qPCR) assay for the Aspergillus genus did not show elevated concentrations of Aspergillus or particulate matter with a diameter of 5 μm or less in patient areas. Air samples from the construction zone indicated the containment system, which used polyethylene film barrier and negative pressure, was effective.

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35

Monteiro, António, and Tiago Almeida. "AC18 residential building, in Lisbon." Metálica, no. 25 (September 30, 2022): 10–12. http://dx.doi.org/10.30779/cmm_metalica_mi25_01.

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Located in downtown Lisbon, more specifically in the Areeiro area, AC 18 is a residential building with about 7000 m2 of gross area. This building is parallelepiped in shape, consisting of 6 underground floors, a ground floor, and 12 stories high, with plan dimensions of 38 m x 20 m and 38 m x 16 m, in the underground and high floors, respectively.n terms of the structural solution, different approaches were considered for the floors below ground and for the floors above ground. For floors below ground level, it was opted for a reinforced concrete structure solution, since they are destined fo

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36

Pošta, Borna, and Siniša Šadek. "Mathematical model of the NPP Krško PCFV system for the RELAP5 computer code." Journal of Energy - Energija 66, no. 1-4 (2022): 226–40. http://dx.doi.org/10.37798/2017661-4106.

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Containment building is the final barrier for radioactive releases from a nuclear power plant (NPP). Preserving its integrity will minimize these releases even in a case of a severe accident with core degradation and melt discharge in the containment accompanied with the pressure and temperature increase. Installation of a venting system with ability to filter radioactive fission products is a preferred way to deal with the issue in present and future NPPs, especially after the Fukushima accident. Such system, called passive containment filtered venting system (PCFV), was installed in 2013 in

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37

Ryu, Myeong-Rok, and Kweon-Ha Park. "Hydrogen explosion effects at a containment building following a severe accident." Journal of the Korean Society of Marine Engineering 40, no. 3 (2016): 165–73. http://dx.doi.org/10.5916/jkosme.2016.40.3.165.

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38

Jiménez, S., A. Cornejo, L. G. Barbu, A. H. Barbat, and S. Oller. "Failure pressure analysis of a nuclear reactor prestressed concrete containment building." Engineering Structures 236 (June 2021): 112052. http://dx.doi.org/10.1016/j.engstruct.2021.112052.

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39

Song, Hyomin, Sangyong Kim, Yooseok Shin, and Gwang-Hee Kim. "Case Study of Reactor Containment Building Construction in Nuclear Power Plant." Journal of Building Construction and Planning Research 02, no. 03 (2014): 173–82. http://dx.doi.org/10.4236/jbcpr.2014.23016.

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40

Lee, Yun, Yun-Yong Kim, Jung-Hwan Hyun, and Do-Gyeum Kim. "Thermal stress analysis of reactor containment building considering severe weather condition." Nuclear Engineering and Design 270 (April 2014): 152–61. http://dx.doi.org/10.1016/j.nucengdes.2014.01.005.

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41

Kajan, Ivan, Henric Lasseson, Ingmar Persson, and Christian Ekberg. "Interaction of ruthenium tetroxide with surfaces of nuclear reactor containment building." Journal of Nuclear Science and Technology 53, no. 9 (2016): 1397–408. http://dx.doi.org/10.1080/00223131.2015.1120245.

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42

Lucey, Aideen. "Suffering at meaning: containment in crisis." Organisational and Social Dynamics 22, no. 1 (2022): 15–27. http://dx.doi.org/10.33212/osd.v22n1.2022.15.

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When anxiety about survival is high it can interfere with the capacity for containment in organisations. The very anxieties that are in such need of containment can be damaging to ways of functioning that are necessary for containing relationships. In certain organisations the ability to tolerate painful feelings is limited and as a result the capacity for containment is impaired. As a consultant working in these circum-stances the task that is required is that of building or rebuilding the container before thinking, in Bion’s sense, can take place. Having an awareness of the state of the orga

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43

Wu, Xingyi, Xingchao Wang, Xinbo Li, and Jinxin Gong. "Two-Way Time-Dependent Prestress Losses of Prestressed Concrete Containment with Bonded Prestressing Strands." Buildings 13, no. 10 (2023): 2513. http://dx.doi.org/10.3390/buildings13102513.

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Prestressing plays a pivotal role in ensuring the tightness and integrity of prestressed concrete containment in nuclear power plants. The prestress loss reduces the compressive stress in concrete resulting from the prestressing strands and increases the risk of containment leakage under severe accident conditions. Therefore, the accurate prediction of prestress loss is essential for the design and in-service management of prestressed concrete containment. Unlike one-way beams or girders in building structures and bridges, two-way prestressing systems are used in prestressed concrete containme

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44

Shi, Xue-yao, Chang-jiang Yang, Jing-xiang Zhan, and Shu-liang Huang. "ICONE23-1132 FUEL BUILDING HYDROGEN RISK ANALYSIS AFTER CONTAINMENT VENTING UNDER SEVERE ACCIDENT OF XUDAPU NPP." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_72.

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45

Jiang, Xin Bo, Chang Zhi Yang, Biao Tang, and Wei Chen. "Coupled Simulation and Analysis of Wind Environment around Residential Quarter in Hot Summer and Cold Winter Area in China." Advanced Materials Research 726-731 (August 2013): 3627–32. http://dx.doi.org/10.4028/www.scientific.net/amr.726-731.3627.

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Computer aided design is an effective means of wind environment assessment and prediction under complex layout, In this paper, the relationships of contact and containment among wind environment was studied by coupled simulation and analysis of wind environment around residential quarter in hot summer and cold winter area, and analyzed how to fix the layout of indoor and outdoor by simulation software during the operation, and make them reach the requirement of Evaluation standard for green building, at the same time make the ecological effects of the buildings complex to maximize.

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46

Gu, Zhenjie, Xiaopan Jia, and Jincheng Su. "Analysis of the Layout of Passive Safety Systems When the Spent Fuel Pool Is Built in the Containment." Energies 18, no. 4 (2025): 906. https://doi.org/10.3390/en18040906.

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The Spent Fuel Pool (SFP) is part of the fuel handling and storage system and is generally arranged in an independent building on the Nuclear Island (NI) of Nuclear Power Plants (NPPs). According to the HAF102—Safety Regulations for Nuclear Power Plants Design, it is necessary to ensure the smooth implementation of the safety functions of the SFP under various operating conditions. If the SFP is arranged inside containment, its protection requirements for external events will be significantly reduced, but new requirements will be raised for accident response measures inside containment, namely

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Ding, Yuqing, and Shahzma Jaffer. "DEVELOPMENT OF FINITE ELEMENT MODELS FOR THE STUDY OF AGEING EFFECTS IN CANDU 6 CONCRETE CONTAINMENT BUILDINGS." CNL Nuclear Review 5, no. 1 (2016): 37–48. http://dx.doi.org/10.12943/cnr.2015.00060.

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In nuclear power plants (NPPs), concrete containment buildings (CCBs) provide the final physical barrier against the release of radioactive materials into the environment and protect the nuclear structures housed within the containment building. CCBs have to be maintained to ensure leak tightness and sound structural integrity for the safe operation throughout the life of NPPs. However, the integrity of CCBs may be affected by the ageing of its concrete, post-tensioning cables and reinforcing bars (rebars). Finite element models (FEMs) of CANDU 6 CCBs have been developed using 2 independent fi

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Lu, Daogang, Yu Liu, and Xiaojia Zeng. "AP1000 Shield Building Dynamic Response for Different Water Levels of PCCWST Subjected to Seismic Loading considering FSI." Science and Technology of Nuclear Installations 2015 (2015): 1–8. http://dx.doi.org/10.1155/2015/840507.

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Huge water storage tank on the top of many buildings may affect the safety of the structure caused by fluid-structure interaction (FSI) under the earthquake. AP1000 passive containment cooling system water storage tank (PCCWST) placed at the top of shield building is a key component to ensure the safety of nuclear facilities. Under seismic loading, water will impact the wall of PCCWST, which may pose a threat to the integrity of the shield building. In the present study, an FE model of AP1000 shield building is built for the modal and transient seismic analysis considering the FSI. Six differe

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Lin, Wei Ting, Yuan Chieh Wu, An Cheng, and Hui Mi Hsu. "Seismic Testing and Verification of a 1/25 Scaled-Down Reinforced Concrete Specimen for the Reactor Building." Applied Mechanics and Materials 764-765 (May 2015): 1129–33. http://dx.doi.org/10.4028/www.scientific.net/amm.764-765.1129.

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A 1/25 scale-down specimen was constructed of a reinforced concrete reactor building used in the nuclear power plant. The non-demoulding technology and self-consolidating concrete were used to cast the specimen with a length of 2.9 m, width of 2.9 m, height of 2.9 m and weight of 28 tons. The entirety struc-ture was composed of a primary containment (thickness of 10 cm), a secondary containment (thickness of 7.5 cm) and three floors (thickness of 30 and 15 cm). Shaking table tests were conducted on it in the National Center for Research on Earthquake Engineering. Testing results indicated that

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Zheng, Zhi, Xiaolan Pan, and Xu Bao. "Sequential Ground Motion Effects on the Behavior of a Base-Isolated RCC Building." Mathematical Problems in Engineering 2017 (2017): 1–13. http://dx.doi.org/10.1155/2017/3579713.

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The sequential ground motion effects on the dynamic responses of reinforced concrete containment (RCC) buildings with typical isolators are studied in this paper. Although the base isolation technique is developed to guarantee the security and integrity of RCC buildings under single earthquakes, seismic behavior of base-isolated RCC buildings under sequential ground motions is deficient. Hence, an ensemble of as-recorded sequential ground motions is employed to study the effect of including aftershocks on the seismic evaluation of base-isolated RCC buildings. The results indicate that base iso

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