The Experts below are selected from a list of 261 Experts worldwide ranked by ideXlab platform
Abu Khalid Rivai - One of the best experts on this subject based on the ideXlab platform.
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lammps simulation of fecr alloy as the basic component of stainless steel for a high temperature Nuclear Reactor Material
2018Co-Authors: Mardiyanto Mardiyanto, Syahfandi Ahda, Abu Khalid RivaiAbstract:At present, Nuclear Reactor technology that is widely used because of its proven reliability is the gen-III + Nuclear Reactor. Even if it is seen from the aspect of safety and reliability of this generation Reactor, it has been proven, but because Nuclear energy plays a vital role to meet the growing world energy needs, it is necessary to have a type of Nuclear Reactor that is tailored to those needs. The next generation of Nuclear Reactors must meet the requirements of fulfilling safety requirements, be flexible, a longer operating life (more than 60 years), more economical. In order for a Reactor to produce higher power, a longer operating life and more economical, Reactor structure Materials which are capable of being operated at high temperatures are needed. The types of Materials that are expected to meet these requirements include various types of ferritic / martensite steel, austenite, alloy steel containing nickel, and metal glass Materials and ceramic Materials. FeCr metal alloys are alloys that form the metals mentioned above, so it is important to conduct research both in simulation and experiment. Molecular Dynamics simulation of FeCr alloys using Large-scale Atomic/Molecular Massively Parallel Simulator (LAMMPS) has been done to explore their thermodynamic characteristics such as heat treatment, solubility of Cr, atomic radial distribution function (RDF).
I. Toth - One of the best experts on this subject based on the ideXlab platform.
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Mössbauer Spectroscopy on Nuclear Power Plant Materials
Hyperfine Interactions, 2002Co-Authors: V. Slugen, J. Lipka, I. TothAbstract:Experimental results of original irradiated Reactor pressure vessel surveillance specimens are presented and discussed in the paper. In 1994, the new “Extended Surveillance Specimen Program for Nuclear Reactor Material Study” was started in collaboration with the Nuclear power plant (NPP) Bohunice and NPP Research Institute Trnava (Slovakia). Three batches of special prepared “Mössbauer samples” (after 1, 2 and 3 years stay in irradiation channels) were measured and interpreted using the new four components approach of Mössbauer spectra evaluation with the aim to observe microstructural changes due to thermal and neutron treatment resulting from operating conditions in NPP. The systematic changes in the relative areas of Mössbauer spectra components were observed and discussed.
Bradley R. Johnson - One of the best experts on this subject based on the ideXlab platform.
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Meso-Scale Magnetic Signatures for Nuclear Reactor Steel Irradiation Embrittlement Monitoring
2015Co-Authors: Jonathan D. Suter, Pradeep Ramuhalli, John S. Mccloy, Weilin Jiang, Danny J. Edwards, Alan L. Schemer-kohrn, Bradley R. JohnsonAbstract:Verifying the structural integrity of passive components in light water and advanced Reactors will be necessary to ensure safe, long-term operations of the existing U.S. Nuclear fleet. This objective can be achieved through nondestructive condition monitoring techniques, which can be integrated with plant operations to quantify the “state of health” of structural Materials in real-time. While nondestructive methods for monitoring many classes of degradation (such as fatigue or stress corrosion cracking) are relatively advanced, this is not the case for degradation caused by irradiation. The development of nondestructive evaluation technologies for these types of degradation will require advanced Materials characterization techniques and tools that enable comprehensive understanding of Nuclear Reactor Material microstructural and behavioral changes under extreme operating environments. Irradiation-induced degradation of Reactor steels causes changes in their microstructure that impacts their micro-magnetic...
Nikolay Ivanov Kolev - One of the best experts on this subject based on the ideXlab platform.
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Coolability of layers of molten Reactor Material
Multiphase Flow Dynamics 4, 2009Co-Authors: Nikolay Ivanov KolevAbstract:Chapter 15 is devoted to the coolability of layers of molten Nuclear Reactor Material. Such physics is important for designing of stabilization of spread melt in Reactor compartments. After defining the problem with its boundary conditions and some simplifying assumptions the system of differential equations describing the process is presented: mass and energy conservation. The following effects are taken into account: the molten steal dropped in the melt or originating inside the melt; the gas release from a sub-layer; the viscous layer; the crust formation; the buoyancy driven convection; the film boiling; the heat conduction through the structures; oxide crust formation on colder heat conducting structures. The existence of a metallic layer is also considered. Some test cases are presented to make easy the application of the presented models: oxide over metal and oxide besides metal. A simple model for gravitational flooding of hot solid horizontal surface by water leading to hyperbolic system is also presented.
Mardiyanto Mardiyanto - One of the best experts on this subject based on the ideXlab platform.
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lammps simulation of fecr alloy as the basic component of stainless steel for a high temperature Nuclear Reactor Material
2018Co-Authors: Mardiyanto Mardiyanto, Syahfandi Ahda, Abu Khalid RivaiAbstract:At present, Nuclear Reactor technology that is widely used because of its proven reliability is the gen-III + Nuclear Reactor. Even if it is seen from the aspect of safety and reliability of this generation Reactor, it has been proven, but because Nuclear energy plays a vital role to meet the growing world energy needs, it is necessary to have a type of Nuclear Reactor that is tailored to those needs. The next generation of Nuclear Reactors must meet the requirements of fulfilling safety requirements, be flexible, a longer operating life (more than 60 years), more economical. In order for a Reactor to produce higher power, a longer operating life and more economical, Reactor structure Materials which are capable of being operated at high temperatures are needed. The types of Materials that are expected to meet these requirements include various types of ferritic / martensite steel, austenite, alloy steel containing nickel, and metal glass Materials and ceramic Materials. FeCr metal alloys are alloys that form the metals mentioned above, so it is important to conduct research both in simulation and experiment. Molecular Dynamics simulation of FeCr alloys using Large-scale Atomic/Molecular Massively Parallel Simulator (LAMMPS) has been done to explore their thermodynamic characteristics such as heat treatment, solubility of Cr, atomic radial distribution function (RDF).
