Results 31 to 40 of about 1,033,988 (155)
Heat Transfer Boundary Conditions in the RELAP5-3D Code [PDF]
Volume 3: Thermal Hydraulics; Instrumentation and Controls, 2008 The heat transfer boundary conditions used in the RELAP5-3D computer program have evolved over the years. Currently, RELAP5-3D has the following options for the heat transfer boundary conditions: (a) heat transfer correlation package option, (b) non-convective option (from radiation/conduction enclosure model or symmetry/insulated conditions), and (c ...
Riemke, Richard A. +2 more
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Thermal hydraulic simulations of the Angra 2 PWR
EPJ Nuclear Sciences & Technologies, 2015 Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant is a pressurized water reactor (PWR) type with electrical output of about 1350 MW.
González-Mantecón Javier +6 more
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Thermal study of the modular high-temperature gas-cooled reactor
Brazilian Journal of Radiation Sciences, 2022 The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is an advanced power plant being a coupling between a modular helium cooled reactor and a gas turbine.
Antonella Lombardi Costa +4 more
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Brayton cycle numerical modeling using the RELAP5-3D code, version 4.3.4
Brazilian Journal of Radiation Sciences, 2019 This work contributes to enable and develop technologies to mount fast microreactors, to generate heat and electric energy, for the purpose to warm and to supply electrically spacecraft equipment and, also, the production of nuclear space propulsion ...
Eduardo Pedroso Longhini +4 more
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Extremely Accurate Sequential Verification of RELAP5-3D
Nuclear Science and Engineering, 2016 Large computer programs like RELAP5-3D solve complex systems of governing, closure and special process equations to model the underlying physics of nuclear power plants. Further, these programs incorporate many other features for physics, input, output, data management, user-interaction, and post-processing.
G. L. Mesina +2 more
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Reformulation RELAP5-3D in FORTRAN 95 and Results [PDF]
ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 2010 RELAP5-3D is a nuclear power plant code used worldwide for safety analysis, design, and operator training. In keeping with ongoing developments in the computing industry, we have re-architected the code in the FORTRAN 95 language [2], the current, fully-available, ANSI standard FORTRAN language.
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Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
Science and Technology of Nuclear Installations, 2009 The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures.
Lap-Yan Cheng, Thomas Y. C. Wei
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Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 Supercritical CO2 Brayton cycle is a good choice of thermal‐to‐electric energy conversion system, which owns a high cycle efficiency and a compact cycle configuration. It can be used in many power‐generation applications, such as nuclear power, concentrated solar thermal, fossil fuel boilers, and shipboard propulsion system. Transient analysis code for
Pan Wu +3 more
wiley +1 more source
Study of Fast Transient Pressure Drop in VVER‐1000 Nuclear Reactor Using Acoustic Phenomenon
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 This article aims to simulate the sudden and fast pressure drop of VVER‐1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations should be solved concurrently by means of DRAGON 4 and DONJON 4 coupling codes.
Soroush Heidari Sangestani +4 more
wiley +1 more source
Modeling Loss‐of‐Flow Accidents and Their Impact on Radiation Heat Transfer
Science and Technology of Nuclear Installations, Volume 2017, Issue 1, 2017., 2017 Long‐term high payload missions necessitate the need for nuclear space propulsion. The National Aeronautics and Space Administration (NASA) investigated several reactor designs from 1959 to 1973 in order to develop the Nuclear Engine for Rocket Vehicle Application (NERVA).
Jivan Khatry +2 more
wiley +1 more source