Automated, Highly Accurate Verification of RELAP5-3D [PDF]
Volume 2B: Thermal Hydraulics, 2014 Computer programs that analyze light water reactor safety solve complex systems of governing, closure and special process equations to model the underlying physics. In addition, these programs incorporate many other features and are quite large. RELAP5-3D[1] has over 300,000 lines of coding for physics, input, output, data management, user-interaction,
George L. Mesina +2 more
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Estudi termoenergètic i dinàmic de transitoris de Centrals Nuclears amb finalitat de seguretat. Optimització de la sistemàtica de càlcul i organització de resultats [PDF]
, 2003 L’objectiu principal d’aquest projecte és l’obtenció d’una biblioteca de casos que contingui de forma estructurada la documentació i els resultats dels estudis dels principals transitoris, tant reals com hipotètics, de les Centrals Nuclears d’Ascó i ...
Gavaldà Sobrepere, Sònia +1 more
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Accident Analysis in Research Reactors [PDF]
The first Research Reactor reaches its criticality on 2nd December 1942. Nowadays, more than 300 research reactors are currently in operation. Over the past fifty years, research reactors have progressed through a variety of tasks.
Adorni, Martina
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Code Development in Coupled PARCS/RELAP5 for Supercritical Water Reactor
Science and Technology of Nuclear Installations, 2014 The new capability is added to the existing coupled code package PARCS/RELAP5, in order to analyze SCWR design under supercritical pressure with the separated water coolant and moderator channels. This expansion is carried out on both codes.
Po Hu, Paul Wilson
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Modeling Moving Systems with RELAP5-3D
Nuclear Science and Engineering, 2016 RELAP5-3D is typically used to model stationary, land-based reactors. However, it can also model reactors in other inertial and accelerating frames of reference. By changing the magnitude of the gravitational vector through user input, RELAP5-3D can model reactors on a space station or the moon.
G. L. Mesina +3 more
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RELAP5-3D thermal hydraulic analysis of the target cooling system in the SPES experimental facility [PDF]
, 2014 The SPES (Selective Production of Exotic Species) experimental facility, under construction at the Italian National Institute of Nuclear Physics (INFN) Laboratories of Legnaro, Italy, is a second generation Isotope Separation On Line (ISOL) plant for ...
Buffa, P. +4 more
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Atom Indonesia, 2019 In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident.
A.R. Antariksawan +7 more
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Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]
Heliyon, 2023 Agbevanu KT +3 more
europepmc +1 more source
Calvert Cliffs RELAP5/MOD3/SCDAP plant deck [PDF]
, 1992 This report documents the development of a RELAP5/MOD3/SCDAP input deck for the Calvert Cliffs nuclear power plant. Through the addition of SCDAP inputs, NPA interactive capabilities, and significant nodalization enhancements the range of applicability; of this input deck has been greatly increased.
Hendrix, C. E., Determan, J. C.
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Accident Management Actions In An Upper-Head Small-Break Loss-Of-Coolant Accident With High-Pressure Safety Injection Failed [PDF]
, 2011 Since the Three Mile Island accident, an important focus of pressurized water reactor (PWR) transient analyses has been a small-break loss-of-coolant accident (SBLOCA). In 2002, the discovery of thinning of the vessel head wall at the Davis Besse nuclear
Gonzalez Cadelo, Juan +3 more
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