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Showing 1 to 7 of 7 for “"MELCOR"”.
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Investigation of MELCOR and STAR-CCM+ modeling capabilities to accurately predict air ingress rates from small breaks in high temperature gas-cooled reactors
… aims to investigate the modeling capabilities of MELCOR and STAR-CCM+ for small break air ingress events. Initial tests present a generic model to test the effects of forced flow and natural circulation through a break connecting a helium volume with an air volume. These tests range in diameters …
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Analyzing FLUENT CFD models and data to develop fundamental codes to assess the effects of graphite oxidation in an HTGR air ingress accident
… a potential subroutine for nodal codes such as MELCOR to model air ingress events. Because of limitations found in FLUENT, and the limitations of the data set, a simple model of the effects of graphite oxidation reactions and structures was built in MATLAB code and is described. This code is …
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Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl
The primary goal of this work was to enhance MELCOR’s material modelling capabilities via one-way coupling of Thermochimica. MELCOR is a state-of-the-art code used to simulate the severe accident progression of a nuclear power plant. The first objective was developing the capabilities in …
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Visualizing Real Time Vasomotion in vivo Using Optical Coherence Tomography.
… in response to temperature change, by using a Melcor Thermoelectric Temperature Controller (MTTC) to produce local heating in conjunction with Spectral Radar Optical Coherence Tomography (SROCT).
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Recombinación del hidrógeno en dispositivos autocatalíticos pasivos y sus implicaciones en la seguridad de las centrales nucleares
… de ser de caudal forzado. El acoplamiento con MELCOR 1.8.5 permite seguir la dinámica de evolución de la atmósfera y se ha validado con los experimentos de la serie Zx en la Battelle Model Containment. Finalmente, se ha demostrado la viabilidad del acoplamiento del modelo con códigos tipo CFD …
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Integrating geographic information systems with the Level 3 Probabilistic Risk Assessment of nuclear power plants to advance modeling of socio-technical infrastructure in emergency response applications
… consequence modeling. In a Level 3 PRA, the MELCOR Accident Consequence Code System (MACCS2) developed by Sandia National Laboratory, is used by the U.S. Nuclear Regulatory Commission and nuclear industry in order to estimate the damages to public health and environment in the case of an NPP …
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Dynamic simulation of nuclear hydrogen production systems
… by using legacy codes, such as RELAP and MELCOR, and their focus has been the operation of nuclear power plants. However, traditional legacy codes are not appropriate to simulate nuclear hydrogen production. The simulation of a nuclear reactor itself is already complex because it involves …