Works matching DE "COOLANT loss in water cooled reactors"
Results: 38
Laser-based sensor for a coolant leak detection in a nuclear reactor.
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- Applied Physics B: Lasers & Optics, 2010, v. 100, n. 2, p. 437, doi. 10.1007/s00340-010-3947-4
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- Article
Numerical and Experimental Study of Thermal Stratification Outside a Small SMR Containment Vessel.
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- Sustainability (2071-1050), 2018, v. 10, n. 7, p. 2332, doi. 10.3390/su10072332
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- Article
Computational Investigation of Film Cooling from Trenched Holes Near the Leading Edge of a Turbine Blade.
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- Numerical Heat Transfer: Part A -- Applications, 2008, v. 53, n. 3, p. 308, doi. 10.1080/10407780701564200
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- Article
Light water reactor fuel performance: Current status, challenges, and future high fidelity modeling.
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- JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 49, doi. 10.1007/s11837-011-0138-7
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- Article
Chromate In coolant water of gramophone record presses.
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- 1978
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- Case Study
ROSA/LSTF Tests and Posttest Analyses by RELAP5 Code for Accident Management Measures during PWR Station Blackout Transient with Loss of Primary Coolant and Gas Inflow.
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- Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/7635878
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- Article
Testing of five 30-year-old prestressed concrete beams.
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- PCI Journal, 2010, p. 50, doi. 10.15554/pcij.09012010.50.58
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- Article
An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient.
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- EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/2016009
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- Article
Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/ LSTF test 7.
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- EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/e2015-50020-7
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- Article
Cooling the intact loop of primary heat transport system using Shutdown Cooling System in case of LOCA events.
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- EPJ Nuclear Sciences & Technologies, 2015, v. 1, p. 1, doi. 10.1051/epjn/e2015-50024-y
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- Article
Physical-chemical Background of the Potential Phase Transitions during Loss of Coolant Accidents in the Supercritical Water Loops of Various Generation IV Nuclear Reactor Types.
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- Periodica Polytechnica: Chemical Engineering, 2019, v. 63, n. 2, p. 333, doi. 10.3311/PPch.12770
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- Article
Determination of Loss of Coolant Accident (LOCA) in Nuclear Power Plants Using Signal Processing Method.
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- Engineering Letters, 2009, v. 17, n. 4, p. 305
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- Article
Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept.
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- Science & Technology of Nuclear Installations, 2015, p. 1, doi. 10.1155/2015/865829
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- Article
Modelling of QUENCH-03 and QUENCH-06 Experiments Using RELAP/SCDAPSIM and ASTEC Codes.
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- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/849480
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- Article
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
PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/548513
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- Article
Failure Assessment Methodologies for Pressure-Retaining Components under Severe Accident Loading.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/487371
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- Article
Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/480948
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- Article
Consistent Posttest Calculations for LOCA Scenarios in LOBI Integral Facility.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/474162
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- Article
The Integral Test Facility Karlstein.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/439374
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- Article
Major Achievements and Prospect of the ATLAS Integral Effect Tests.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/375070
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- Article
Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/305405
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- Article
Severe Accident Simulation of the Laguna Verde Nuclear Power Plant.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/209420
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- Article
Application of CFD Codes in Nuclear Reactor Safety Analysis.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/198758
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- Article
CFD Application to Hydrogen Risk Analysis and PAR Qualification.
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- Science & Technology of Nuclear Installations, 2009, v. 2009, p. 1, doi. 10.1155/2009/213981
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- Article
An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model.
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- Science & Technology of Nuclear Installations, 2008, p. 1, doi. 10.1155/2008/498737
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- Article
GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications.
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- Science & Technology of Nuclear Installations, 2008, p. 1, doi. 10.1155/2008/798901
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- Article
Concept of a demonstrational hybrid reactor-a tokamak with molten-salt blanket for U fuel production: 1. Concept of a stationary Tokamak as a neutron source.
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- Physics of Atomic Nuclei, 2015, v. 78, n. 12, p. 1326, doi. 10.1134/S1063778815120017
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- Article
Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle.
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- Physics of Atomic Nuclei, 2011, v. 74, n. 13, p. 1854, doi. 10.1134/S1063778811130011
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- Article
Public Response to a Near‐Miss Nuclear Accident Scenario Varying in Causal Attributions and Outcome Uncertainty.
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- Risk Analysis: An International Journal, 2018, v. 38, n. 5, p. 947, doi. 10.1111/risa.12920
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- Article
A Thermoelectric Generator Using Engine Coolant for Light-Duty Internal Combustion Engine-Powered Vehicles.
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- Journal of Electronic Materials, 2011, v. 40, n. 5, p. 812, doi. 10.1007/s11664-011-1580-6
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- Article
Verification and validation of numerical models of the transport of insulation debris.
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- Journal of Computational Multiphase Flows, 2012, v. 4, n. 3, p. 255, doi. 10.1260/1757-482X.4.3.255
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- Article
A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA.
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- Energies (19961073), 2016, v. 9, n. 8, p. 578, doi. 10.3390/en9080578
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- Article
Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor.
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- Atomic Energy, 2017, v. 122, n. 4, p. 217, doi. 10.1007/s10512-017-0259-3
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- Article
Determination of the region of vibroacoustic resonances of coolant and fuel assemblies in advanced enhanced-power reactors.
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- Atomic Energy, 2010, v. 108, n. 3, p. 194, doi. 10.1007/s10512-010-9276-1
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- Article
Supercritical-pressure water cooled thermal reactor with uranium–plutonium–thorium fuel cycle and bidirectional coolant flow articles.
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- Atomic Energy, 2009, v. 106, n. 5, p. 305, doi. 10.1007/s10512-009-9169-3
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- Article
Method for fast separation of iodine isotopes on silver-containing membranes.
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- Atomic Energy, 2008, v. 104, n. 4, p. 313, doi. 10.1007/s10512-008-9034-9
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- Article
Evaluation of the technological parameters of a high-temperature reactor with solid coolant in the electricity generating regime.
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- Atomic Energy, 2008, v. 104, n. 4, p. 268, doi. 10.1007/s10512-008-9027-8
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- Publication type:
- Article