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Journal articles on the topic 'Containment building'

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Author: Grafiati

Published: 10 December 2022

Last updated: 29 January 2023

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1

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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2

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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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 (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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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 (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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5

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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6

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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7

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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8

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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9

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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10

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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11

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 intersection between the “politics of containment” and the “politics of invisibility”.

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12

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 In-Containment Relief Valve (ICRV) from steam generator (SG) to the free space in the containment building and it was simulated by MELCOR code for numerical analysis. Simulation results show that the radioactive nuclides were not released to the environment in the ICRV case. However, the containment pressure increased more than the base case, which is a disadvantage of the ICRV. To minimize the negative effects of the ICRV, the ICRV linked to Reactor Drain Tank (RDT) and cavity flooding was performed. Because the overpressurization of containment is due to heat of ex-vessel corium, only cavity flooding was effective for depressurization. The conceptual design of the ICRV is effective in mitigating the SGTR accident.

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13

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 (December 1, 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 revolution of part of the structure.By combining the results produced by the various models and accounting for discontinuities caused by openings, etc., a complete picture of the forces, displacements, or accelerations existing in the reactor building under operating conditions and during postulated accidents or seismic events may be drawn.This process has been partly automated by the development of relevant software. A flow chart of the whole analysis process is given. Key words: nuclear power plants, reactor building, containment, analysis, static, seismic, finite elements.

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14

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 (April 30, 2013): 157–64. http://dx.doi.org/10.7734/coseik.2013.26.2.157.

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15

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 (January 2004): 143–53. http://dx.doi.org/10.1016/j.nucengdes.2003.09.001.

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16

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

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17

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 or total underground placement of nuclear power plant would reduce its visibility, and thus, public concerns would also be reduced. However, many design, operational, and economic disadvantages are linked with the underground placement of nuclear power plants. The aim of this paper is to provide state-of-the-art review of existing underground nuclear reactors, conceptual designs of underground nuclear reactors, and related literature, which can later be used for the design of a underground reinforced concrete containment building.

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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 variable speed primary pumps, and with an upgrade in the safety boration function. Decay heat removal in shutdown conditions is realized through the secondary side rather than through primary side equipment. The compact RCS can be installed in a small volume, high-pressure containment. The containment is divided into two leak-tight zones separated by a partition plate. Safety equipment installed in one of the two zones will be protected against adverse ambient conditions from leaks or breaks in the other zone. The partition facilitates management of coolant inventory within the RCS and the containment following RCS leaks or breaks. In particular, the safety injection system as commonly known, consisting of accumulators and multiple stages of injection pumps can be discarded and replaced by gravity-driven flooding tanks. Space available around major RCS components is adequate to avoid compromising accessibility during maintenance or in-service inspection operations. In addition, the two-zone, high-pressure containment provides extra margins in severe accident mitigation. Finally, the proposed containment has a much smaller size than customary large dry containments in PWR practice and it can be anticipated that Nuclear Island building size will similarly be reduced.

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19

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 (December 30, 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 for steam removal by condensation on large steel containment structure is a major contributing process, controlling the pressure and temperature maximum reached during the accident event. The results are analyzed, discussed and compared with the similar work done by Sandia National Laboratories.

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20

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

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21

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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22

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

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23

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 the yield strength of the steel liner material. Accordingly, the liner integrity is preserved, the containment remains operable and ensures compliance of radiation safety requirements.

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24

Wang, Xiaolei, and Dagang Lu. "Finite Element Reliability Analysis of Steel Containment Vessels with Corrosion Damage." Journal of Disaster Research 10, no. 3 (June 1, 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 analysis of containment vessels can be conducted by using Monte Carlo Simulation (MCS) or Latin Hypercube Sampling (LHS) with the deterministic finite element analysis. In this paper, a 3D finite element model of an AP1000 steel containment vessel is constructed using the general-purpose nonlinear finite element analysis program ABAQUS. Then the finite element reliability method (FERM) based on the first order reliability method (FORM) is applied to analyze the reliability of the steel containment vessel, which is implemented by combining ABAQUS and MATLAB software platforms. The reliability and sensitivity indices of steel containment vessels under internal pressure with and without corrosion damage are obtained and compared. It is found that the FERM-based procedure is very efficient to analyze reliability and sensitivity of nuclear power plant structures.

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25

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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26

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 (October 1, 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 structure has not yet been adopted for the CV. An SFR CV has a lower pressure environment than the LWR CV, although the environmental temperature of the SFR is much higher than that of the LWR in the postulated coolant leakage accident. It is therefore important to investigate its characteristics at high temperature to adopt the SC structure to the JSFR CV because the CV keeps containment functions in accidents to be assumed in design. This paper describes the construction of the design evaluation method from design (construction period shortening) and accident management, experimental, and analytical points of view.

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27

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 (March 31, 2016): 165–73. http://dx.doi.org/10.5916/jkosme.2016.40.3.165.

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28

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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29

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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30

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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31

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 (January 8, 2016): 1397–408. http://dx.doi.org/10.1080/00223131.2015.1120245.

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32

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 (March 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 methods.

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33

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 (May 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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34

Lucey, Aideen. "Suffering at meaning: containment in crisis." Organisational and Social Dynamics 22, no. 1 (June 19, 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 organisational container can help the consultant to make a judgement about the level of complexity they are likely to encounter in the work and enable them to plan interventions accordingly. Using examples from my consultancy practice I describe a process of “suffering at meaning” as the way in which containing relationships might be developed so that painful experiences can be faced.

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35

Chavez, Maria, and Kristina Warren. "A Sound Artist’s Breakdown of Field Recording over History." Organised Sound 27, no. 1 (April 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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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 (June 23, 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 the NPP Krško. Thermal hydraulic model of the PCFV system which included aerosol and iodine filters, associated pipings and valves was developed for the best-estimate computer code RELAP5. Main results and discussion are presented and compared with relevant plant documentation.

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37

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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38

Park, Kweonha, and Khor Chong Lee. "Proposal and Analysis of Hydrogen Mitigation System Guiding Hydrogen in Containment Building." Journal of the Korean Society of Marine Engineering 39, no. 5 (June 30, 2015): 516–21. http://dx.doi.org/10.5916/jkosme.2015.39.5.516.

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39

Byon, Jihyang, Sangjune Park, and Seokyoung Ahn. "Radionuclide-Specific Exposure Pathway Analysis of Kori Unit 1 Containment Building Surface." Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) 18, no. 3 (September 30, 2020): 347–54. http://dx.doi.org/10.7733/jnfcwt.2020.18.3.347.

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Lee, Seung-Hwan, Nam-Kwon Lee, Geum-Seok Lee, Hong-Pyo Lee, and Yun-Sik Yu. "Structural Health Monitoring of Nuclear Containment Building Using Fiber Bragg Grating Sensor." Journal of Sensor Science and Technology 22, no. 1 (January 31, 2013): 71–75. http://dx.doi.org/10.5369/jsst.2013.22.1.71.

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41

Jeon, Se-Jin, and Chul-Hun Chung. "Axisymmetric Modeling of Dome Tendons in Nuclear Containment Building I. Theoretical Derivations." Journal of the Korea Concrete Institute 17, no. 4 (August 1, 2005): 521–26. http://dx.doi.org/10.4334/jkci.2005.17.4.521.

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42

Lee, Kyoungsoo, Sang Eul Han, and Jung-Wuk Hong. "Analysis of impact of large commercial aircraft on a prestressed containment building." Nuclear Engineering and Design 265 (December 2013): 431–49. http://dx.doi.org/10.1016/j.nucengdes.2013.09.009.

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43

Fernández-Cosials, Kevin, Zuriñe Goñi, Gonzalo Jiménez, César Queral, and Javier Montero. "Three-dimensional simulation of a LBLOCA in an AP1000 ® containment building." Energy Procedia 127 (September 2017): 234–41. http://dx.doi.org/10.1016/j.egypro.2017.08.124.

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44

Andreoli, Valter, Paolo Angeloni, Paolo Contri, and Luigi Brusa. "Numerical simulation of the ultimate load capacity of a reactor containment building." Nuclear Engineering and Design 145, no. 3 (December 1993): 403–17. http://dx.doi.org/10.1016/0029-5493(93)90249-9.

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45

Lee, Un-Jang, and Goon-Cherl Park. "Experimental study on hydrogen behavior at a subcompartment in the containment building." Nuclear Engineering and Design 217, no. 1-2 (August 2002): 41–47. http://dx.doi.org/10.1016/s0029-5493(02)00136-x.

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46

NUMATA, Shigeo, Kiyoshi MINAMI, Yasuhiko FUJII, and Makoto OKAMOTO. "Containment of Tritiated Water Vapor by Concrete Walls of Fusion Reactor Building." Journal of Nuclear Science and Technology 28, no. 7 (July 1991): 678–84. http://dx.doi.org/10.1080/18811248.1991.9731410.

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47

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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Abstract:

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 isolation can significantly attenuate the earthquake shaking of the RCC building under not only single earthquakes but also seismic sequences. It is also found that the adverse aftershock effect on the RCC can be reduced due to the base isolation applied to the RCC. More importantly, the study indicates that disregarding aftershocks can induce significant underestimation of the isolator displacement for base-isolated RCC buildings.

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Clubley, S. K., and M. E. J. Morey. "Strengthening rail bridge wingwalls for containment barriers." Proceedings of the Institution of Civil Engineers - Bridge Engineering 157, no. 3 (September 2004): 163–70. http://dx.doi.org/10.1680/bren.2004.157.3.163.

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Iqbal, Javed. "Containment evaluation against ground shock in rock." Proceedings of the Institution of Civil Engineers - Structures and Buildings 167, no. 2 (February 2014): 108–22. http://dx.doi.org/10.1680/stbu.11.00034.

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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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Abstract:

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 different water levels in PCCWST were discussed by comparing the modal frequency, seismic acceleration response, and von Mises stress distribution. The results show the maximum von Mises stress emerges at the joint of shield building roof and water around the air inlet. However, the maximum von Mises stress is below the yield strength of reinforced concrete. The results may provide a reference for design of the AP1000 and CAP1400 in the future.

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