Works matching DE "NUCLEAR reactor containment"
Results: 38
Can We Design Concrete to Survive Nuclear Environments? A summary of a panel discussion on the effects of nuclear environments on concrete and cementitious grouts.
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- Concrete International, 2017, v. 39, n. 11, p. 29
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Household salt for retrospective dose assessments using OSL: signal integrity and its dependence on containment, sample collection, and signal readout.
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- Radiation & Environmental Biophysics, 2014, v. 53, n. 3, p. 559, doi. 10.1007/s00411-014-0544-7
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Contribution of multiscale materials modelling for underwriting nuclear pressure vessel integrity.
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- Materials Science & Technology, 2004, v. 20, n. 5, p. 553, doi. 10.1179/026708304225016707
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Weibull Modulus of Cleavage Fracture Toughness of Ferritic Steels.
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- Metallurgical & Materials Transactions. Part A, 2021, v. 52, n. 4, p. 1503, doi. 10.1007/s11661-021-06169-w
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Numerical Analysis for Hydrogen Flame Acceleration during a Severe Accident Initiated by SBLOCA in the APR1400 Containment.
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- Hydrogen, 2022, v. 3, n. 1, p. 28, doi. 10.3390/hydrogen3010002
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Effect of Temperature Gradient on Chloride Ion Diffusion in Nuclear Reactor Containment Building Concrete.
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- Energies (19961073), 2022, v. 15, n. 15, p. 5581, doi. 10.3390/en15155581
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Ultrasonic monitoring of stress and cracks of the 1/3 scale mock-up of nuclear reactor concrete containment structure.
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- Structural Health Monitoring, 2022, v. 21, n. 4, p. 1474, doi. 10.1177/14759217211034729
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The Importance of Establishing and Maintaining Continuity of Knowledge During 21stCentury Nuclear Fuel Cycle Activities.
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- Journal of the Institute of Nuclear Materials Management, 2012, v. 40, n. 4, p. 86
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Containment of a reactor meltdown.
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- Bulletin of the Atomic Scientists, 1982, v. 38, n. 7, p. 52, doi. 10.1080/00963402.1982.11455779
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New lumped-mass-stick model based on modal characteristics of structures: development and application to a nuclear containment building.
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- Earthquake Engineering & Engineering Vibration, 2013, v. 12, n. 2, p. 307, doi. 10.1007/s11803-013-0173-1
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A novel strategy for iodine removal from nuclear reactor accidental gases: efficient adsorption of CH<sub>3</sub>I on the moderately hydrophobic modified silver-loaded zeolite under high temperature and humidity conditions.
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- Journal of Nuclear Science & Technology, 2025, v. 62, n. 1, p. 43, doi. 10.1080/00223131.2024.2379881
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Optimal Protection of Reactor Hall Under Nuclear Fuel Container Drop Using Simulation Methods.
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- Transactions of the VSB - Technical University of Ostrava, Civil Engineering Series, 2014, v. 14, n. 2, p. 69, doi. 10.2478/tvsb-2014-0020
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- Article
Experimental and Numerical Studies on Sloshing Dynamics of PCS Water Tank of Nuclear Island Building.
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- Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/5094810
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Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/1450648
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Assessment of the MARS Code Using the Two-Phase Natural Circulation Experiments at a Core Catcher Test Facility.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/5731420
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Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/8431934
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PWR circuit contamination assessment tool. Use of OSCAR code for engineering studies at EDF.
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- EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/e2016-50038-4
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Correlation Analysis of Earthquake Intensity Measures and Engineering Demand Parameters of Reactor Containment Structure.
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- Engineering, Technology & Applied Science Research, 2022, v. 12, n. 5, p. 9160
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Fukushima in review: A complex disaster, a disastrous response.
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- Bulletin of the Atomic Scientists, 2012, v. 68, n. 2, p. 9, doi. 10.1177/0096340212440359
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Validation and Application of a Code for Three-Dimensional Analysis of Hydrogen–Steam Behavior in a Nuclear Reactor Containment during Severe Accidents.
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- Applied Sciences (2076-3417), 2024, v. 14, n. 15, p. 6695, doi. 10.3390/app14156695
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FALLOUTS FROM CHERNOBYL.
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- Environment, 1988, v. 30, n. 3, p. 1, doi. 10.1080/00139157.1988.9928893
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Assessment of Prediction Capabilities of COCOSYS and CFX Code for Simplified Containment.
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- Science & Technology of Nuclear Installations, 2016, p. 1, doi. 10.1155/2016/9542121
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Study on the Behaviors of a Conceptual Passive Containment Cooling System.
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- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/358365
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- Article
Large-Scale Containment Cooler Performance Experiments under Accident Conditions.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/943197
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- Article
A model of hydrogen passive autocatalytic recombiner and its validation via CFD simulations.
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- Archives of Thermodynamics, 2013, v. 34, n. 4, p. 257, doi. 10.2478/aoter-2013-0042
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- Article
考虑预应力损失影响的安全壳安全性能研究.
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- Atomic Energy Science & Technology, 2023, v. 57, n. 3, p. 600, doi. 10.7538/yzk.2022.youxian.0326
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- Article
Seismic Strength Evaluation of Corroded Reactor Containment Building.
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- International Journal of Concrete Structures & Materials, 2025, v. 19, n. 1, p. 1, doi. 10.1186/s40069-024-00734-4
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- Article
Hydrogen Distribution in Nuclear Reactor Containment During Accidents and Associated Heat and Mass Transfer Issues—A Review.
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- Heat Transfer Engineering, 2015, v. 36, n. 10, p. 859, doi. 10.1080/01457632.2015.965091
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Estimating droplet sizes.
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- Nuclear Future, 2017, v. 13, n. 4, p. 60
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Olkiluoto 3: highest requirements for safety tests and inspections.
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- Nuclear Future, 2014, v. 10, n. 6, p. 37
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Construction starts on third Barakah unit.
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- Nuclear Future, 2014, v. 10, n. 6, p. 13
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PC clean-up at Winfrith.
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- Nuclear Future, 2014, v. 10, n. 2, p. 10
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An overview of GE-Hitachi's Economic Simplified Boiling Water Reactor.
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- Nuclear Future, 2009, v. 5, n. 2, p. 74
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Method for evaluation of concrete containment structure subjected to earthquake excitation and internal pressure increase.
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- Earthquake Engineering & Structural Dynamics, 2018, v. 47, n. 6, p. 1544, doi. 10.1002/eqe.3029
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Beneficial and Detrimental Effects of Soil-Structure Interaction on Probabilistic Seismic Hazard and Risk of Nuclear Power Plant.
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- Advances in Civil Engineering, 2018, p. 1, doi. 10.1155/2018/2698319
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- Article
Computational and Experimental Studies of Mixing of a Light Gas in the ERCOSAM-SAMARA Projects.
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- Atomic Energy, 2017, v. 123, n. 1, p. 1, doi. 10.1007/s10512-017-0292-2
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- Article
Heat-Transfer Modeling in Supercritical Pressure Water Using Other Media.
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- Atomic Energy, 2014, v. 115, n. 4, p. 260, doi. 10.1007/s10512-014-9781-8
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- Article
Experimental Study of a Containment Heat-Removal System on the SMK Stand.
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- Atomic Energy, 2014, v. 115, n. 4, p. 234, doi. 10.1007/s10512-014-9777-4
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- Article