The Experts below are selected from a list of 39 Experts worldwide ranked by ideXlab platform
Shripad T Revankar - One of the best experts on this subject based on the ideXlab platform.
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high pressure simulation experiment on corium dispersion in direct containment heating
Nuclear Engineering and Design, 1996Co-Authors: Q Wu, M Ishii, Shripad T RevankarAbstract:Abstract Purdue 1 10 scale direct containment heating separate effects experiments under a reactor vessel pressure up to 14.2 MPa are presented. With the test facility scaled to the Zion PWR geometry, these tests are mainly focused on the corium dispersion phenomenon in order to obtain a better understanding of the dominant driving mechanisms. Water and Woods Metal have been used separately to simulate the core melt, the reactor vessel being pressurized with nitrogen gas analogous to the steam in the prototypic case. The entire test transient lasted for a few seconds, and the liquid dispersion in the test cavity occurred within only 0.5 s. To synchronize the data acquisition and blowdown transient, the test initiation was triggered by breaking two rupture discs in the liquid/gas delivery system. Parameters characterizing the liquid transport were obtained via various instruments. Important information about the mean size and size distribution of the dispersed droplets in the test cavity, the liquid film flow transient, the subcompartment trapping, and the liquid carry-over to the containment has been obtained. These results, along with data from a previous low pressure (1.4 MPa) experiment carried out at Purdue University, form a solid database for further theoretical analysis.
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high pressure simulation experiment on corium dispersion in direct containment heating
Transactions of the American Nuclear Society, 1995Co-Authors: Q Wu, M Ishii, Shripad T RevankarAbstract:In direct containment heating (DCH) accidents one of the most important factors responsible for containment heating is the dispersion of the corium driven by high-speed steam flow. To investigate the dispersion phenomena, separate-effects tests at Purdue University and integral tests at Argonne National Laboratory and Sandia National Laboratories were previously conducted. With these experiments and some integral tests, a fairly good understanding of the corium dispersion process has been obtained. However, there are still uncertainties in predicting the corium transport behavior for high-pressure melt injection cases under prototypical pressures up to 14 MPa. For this purpose, the 1:10 scale DCH separate-effects experiments under reactor vessel pressures up to 14.2 MPa are being carried out at Purdue with water and Woods Metal simulating the core melt. The objective of this paper is to present the major work completed and some important test results concerning the liquid dispersion in the test cavity as well as in the containment dorm, which include the mean droplet size, the liquid film velocity, and the gas velocity. A brief discussion is provided on liquid dispersion and transport in the accident transient.
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simulation experiment on corium dispersion in direct containment heating using air water and air Woods Metal
Transactions of the American Nuclear Society, 1994Co-Authors: G J Zhang, Q Wu, M Ishii, Shripad T RevankarAbstract:One of the deficiencies of previous direct containment heating (DCH) studies is the lack of understanding and modeling of corium entrainment and droplet dispersion process. For this reason, separate-effects experiments and a scaling study on DCH phenomena were undertaken to fill this void. This paper is focused on the experimental investigation of separate effects of liquid entrainment and droplet dispersion using air-water and air-Woods Metal as simulants.
Q Wu - One of the best experts on this subject based on the ideXlab platform.
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high pressure simulation experiment on corium dispersion in direct containment heating
Nuclear Engineering and Design, 1996Co-Authors: Q Wu, M Ishii, Shripad T RevankarAbstract:Abstract Purdue 1 10 scale direct containment heating separate effects experiments under a reactor vessel pressure up to 14.2 MPa are presented. With the test facility scaled to the Zion PWR geometry, these tests are mainly focused on the corium dispersion phenomenon in order to obtain a better understanding of the dominant driving mechanisms. Water and Woods Metal have been used separately to simulate the core melt, the reactor vessel being pressurized with nitrogen gas analogous to the steam in the prototypic case. The entire test transient lasted for a few seconds, and the liquid dispersion in the test cavity occurred within only 0.5 s. To synchronize the data acquisition and blowdown transient, the test initiation was triggered by breaking two rupture discs in the liquid/gas delivery system. Parameters characterizing the liquid transport were obtained via various instruments. Important information about the mean size and size distribution of the dispersed droplets in the test cavity, the liquid film flow transient, the subcompartment trapping, and the liquid carry-over to the containment has been obtained. These results, along with data from a previous low pressure (1.4 MPa) experiment carried out at Purdue University, form a solid database for further theoretical analysis.
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high pressure simulation experiment on corium dispersion in direct containment heating
Transactions of the American Nuclear Society, 1995Co-Authors: Q Wu, M Ishii, Shripad T RevankarAbstract:In direct containment heating (DCH) accidents one of the most important factors responsible for containment heating is the dispersion of the corium driven by high-speed steam flow. To investigate the dispersion phenomena, separate-effects tests at Purdue University and integral tests at Argonne National Laboratory and Sandia National Laboratories were previously conducted. With these experiments and some integral tests, a fairly good understanding of the corium dispersion process has been obtained. However, there are still uncertainties in predicting the corium transport behavior for high-pressure melt injection cases under prototypical pressures up to 14 MPa. For this purpose, the 1:10 scale DCH separate-effects experiments under reactor vessel pressures up to 14.2 MPa are being carried out at Purdue with water and Woods Metal simulating the core melt. The objective of this paper is to present the major work completed and some important test results concerning the liquid dispersion in the test cavity as well as in the containment dorm, which include the mean droplet size, the liquid film velocity, and the gas velocity. A brief discussion is provided on liquid dispersion and transport in the accident transient.
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simulation experiment on corium dispersion in direct containment heating using air water and air Woods Metal
Transactions of the American Nuclear Society, 1994Co-Authors: G J Zhang, Q Wu, M Ishii, Shripad T RevankarAbstract:One of the deficiencies of previous direct containment heating (DCH) studies is the lack of understanding and modeling of corium entrainment and droplet dispersion process. For this reason, separate-effects experiments and a scaling study on DCH phenomena were undertaken to fill this void. This paper is focused on the experimental investigation of separate effects of liquid entrainment and droplet dispersion using air-water and air-Woods Metal as simulants.
Norberto Farfan - One of the best experts on this subject based on the ideXlab platform.
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on the use of Woods Metal for fabricating and testing polymeric organic solar cells an easy and fast method
Solar Energy Materials and Solar Cells, 2011Co-Authors: Josefrancisco Salinas, Joseluis Maldonado, Gabriel Ramosortiz, Mario Rodriguez, M A Menesesnava, O Barbosagarcia, Rosa Santillan, Norberto FarfanAbstract:Abstract In this work, we propose the use of Woods Metal, which is an eutectic alloy of Pb/Bi/Cd/Sn (25%, 50%, 12.5% and 12.5%, respectively), as a convenient substitute to evaporated aluminum for testing polymeric organic photovoltaic (OPVs) devices. The Woods Metal, which melts at 75 °C, was used as cathode and it permits an easy and quick device implementation that can be performed through a vacuum free process. As anode, the commercial and transparent indium tin oxide (ITO) deposited on glass slides was used. OPVs cells were prepared based on 6-nitro-3-(E)-3-(4-dimethylaminophenyl)allylidene)-2,3-dihydrobenzo[d]-[1,3,2]-oxazaborole (M1) and (E)-3-(4-dimethylaminophenyl)allylidene)-2,3-dihydrobenzo[d]-[1,3,2]-oxazaborole (M2), which are conjugated organo-boron molecules, the well known photoconductor polymer MEH–PPV, and the fullerene PC 61 BM as the sensitizer. M1 and M2 were mixed with MEH–PPV to enhance the absorption of the OPVs devices. The OPVs cell electrical performance is acceptable considering the fast evaluation of promising materials.
M Ishii - One of the best experts on this subject based on the ideXlab platform.
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high pressure simulation experiment on corium dispersion in direct containment heating
Nuclear Engineering and Design, 1996Co-Authors: Q Wu, M Ishii, Shripad T RevankarAbstract:Abstract Purdue 1 10 scale direct containment heating separate effects experiments under a reactor vessel pressure up to 14.2 MPa are presented. With the test facility scaled to the Zion PWR geometry, these tests are mainly focused on the corium dispersion phenomenon in order to obtain a better understanding of the dominant driving mechanisms. Water and Woods Metal have been used separately to simulate the core melt, the reactor vessel being pressurized with nitrogen gas analogous to the steam in the prototypic case. The entire test transient lasted for a few seconds, and the liquid dispersion in the test cavity occurred within only 0.5 s. To synchronize the data acquisition and blowdown transient, the test initiation was triggered by breaking two rupture discs in the liquid/gas delivery system. Parameters characterizing the liquid transport were obtained via various instruments. Important information about the mean size and size distribution of the dispersed droplets in the test cavity, the liquid film flow transient, the subcompartment trapping, and the liquid carry-over to the containment has been obtained. These results, along with data from a previous low pressure (1.4 MPa) experiment carried out at Purdue University, form a solid database for further theoretical analysis.
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high pressure simulation experiment on corium dispersion in direct containment heating
Transactions of the American Nuclear Society, 1995Co-Authors: Q Wu, M Ishii, Shripad T RevankarAbstract:In direct containment heating (DCH) accidents one of the most important factors responsible for containment heating is the dispersion of the corium driven by high-speed steam flow. To investigate the dispersion phenomena, separate-effects tests at Purdue University and integral tests at Argonne National Laboratory and Sandia National Laboratories were previously conducted. With these experiments and some integral tests, a fairly good understanding of the corium dispersion process has been obtained. However, there are still uncertainties in predicting the corium transport behavior for high-pressure melt injection cases under prototypical pressures up to 14 MPa. For this purpose, the 1:10 scale DCH separate-effects experiments under reactor vessel pressures up to 14.2 MPa are being carried out at Purdue with water and Woods Metal simulating the core melt. The objective of this paper is to present the major work completed and some important test results concerning the liquid dispersion in the test cavity as well as in the containment dorm, which include the mean droplet size, the liquid film velocity, and the gas velocity. A brief discussion is provided on liquid dispersion and transport in the accident transient.
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simulation experiment on corium dispersion in direct containment heating using air water and air Woods Metal
Transactions of the American Nuclear Society, 1994Co-Authors: G J Zhang, Q Wu, M Ishii, Shripad T RevankarAbstract:One of the deficiencies of previous direct containment heating (DCH) studies is the lack of understanding and modeling of corium entrainment and droplet dispersion process. For this reason, separate-effects experiments and a scaling study on DCH phenomena were undertaken to fill this void. This paper is focused on the experimental investigation of separate effects of liquid entrainment and droplet dispersion using air-water and air-Woods Metal as simulants.
M Rajan - One of the best experts on this subject based on the ideXlab platform.
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role of initial melt inventory on debris generation with Woods Metal water interaction under drop mode
Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Pl, 2008Co-Authors: K S Narayanan, N Kasinathan, G Lydia, S S Murthy, M Kumaresan, J Harvey, M RajanAbstract:Thermal interaction of a hot liquid with a cold volatile liquid was investigated with Woods Metal melt water system at first contact temperature just above the spontaneous nucleation temperature of water. Drop mode experiments were carried out up to 1000 g of melt and resulting debris sizes and shapes were analyzed. Experiment was carried out with melt temperature of 425 °C and water pool at 30 °C. One of the 100 g run resulted in an energetic interaction with a mass median diameter 2.5 mm ± 1.58. The MMD is seen to change to higher values for non-energetic cases and higher melt inventories. Dynamic pressure signals are also recorded. Relative contribution of thermal and hydrodynamic fragmentation is assessed in pool and narrow geometries. Dependence of mass median diameter on initial melt inventory has been brought out.Copyright © 2008 by ASME
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Assessment of Thermal and Hydrodynamic Fragmentation in Molten Fuel Coolant Interaction With Simulant System
Volume 5: Safety and Security; Low Level Waste Management Decontamination and Decommissioning; Nuclear Industry Forum, 2006Co-Authors: K S Narayanan, N Kasinathan, G Lydia, S S Murthy, M Kumaresan, J Harvey, A. Jasmin Sudha, M RajanAbstract:In the Safety analysis of Fast Breeder Reactor, assessment of Molten Fuel Coolant Interaction (MFCI) assumes importance for two aspects, namely the characterization of the debris and severity of pressure pulses generation. An attempt has been made to investigate the debris generation characteristics with molten Woods Metal (Alloy of Bi 50% Pb 25% Sn 12.5% & Cd 12.5% & melting point of 346 K) - Water simulant system. Liquid Woods Metal and liquid Uranium dioxide physical properties (Density, Surface tension & Kinematic viscosity) are similar. Experimental studies were conducted for various melt temperatures covering non-boiling, convective boiling and film boiling regimes of water, to assess the debris generation resulting from both hydrodynamic and thermal interaction. Woods Metal was heated to the desired temperature and poured through a hot funnel having a nozzle of 8 mm release diameter into a water column of height up to 140 cm. Experiments were repeated for different coolant temperature and melt inventory up to 5 kg. The melt entry velocity was determined from video recordings. The debris is analyzed on the basis of interface temperature, Rayleigh-Taylor and Kelvin-Helmholtz instabilities. It is observed that Kelvin-Helmholtz instability is the dominant fragmentation phenomena. Contribution due to coolant boiling resulted in more debris generation in the size less than 4 mm.Copyright © 2006 by ASME
