Results 91 to 100 of about 5,558 (186)
Dynamic PRA: an Overview of New Algorithms to Generate, Analyze and Visualize Data [PDF]
, 2013 State of the art PRA methods, i.e. Dynamic PRA (DPRA) methodologies, largely employ system simulator codes to accurately model system dynamics. Typically, these system simulator codes (e.g., RELAP5 ) are coupled with other codes (e.g., ADAPT, RAVEN
A. Yilmaz +10 more
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Efek Kebocoran Beamtube Dan Pipa Primer Penukar Panas Pada Suatu Model Reaktor Riset 1 Mw Berbahan Bakar Tipe Silinder [PDF]
, 2013 Telah dilakukan analisis transien menggunakan program komputer RELAP5/Mod3.2 terhadap model reaktor riset berbahan bakar tipe silinder daya 1 MW dan diasumsikan mengalami kebocoran pada beamtube, pipa cold leg, dan pipa hot leg.
Nazar, R. N. (Reinaldy)
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RELAP5/MOD3 subcooled boiling model assessment [PDF]
, 1998 This report presents the assessment of the RELAP5/Mod3 (5m5 version) code subcooled boiling process model which is based on a variety of experiments. The accuracy of the model is confirmed for a wide range of regime parameters for the case of uniform heating along the channel.
Devkin, A. S., Podosenov, A. S.
openaire +2 more sources
Avaluació del software SNAP i TRACE com a eina d’anàlisi termohidràulica. Cas pràctic [PDF]
, 2016 Les simulacions computacionals són un dels mètodes de treball més usats en l’actualitat dins el camp de l’enginyeria. En l’enginyeria nuclear en particular, es fan servir les simulacions termohidràuliques mitjançant diferents codis de càlcul. Els codis
Cheng-Ping Chiang, Mi
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Science and Technology of Nuclear Installations, 2010 The behaviour of a parallel-channel natural circulation boiling water reactor under a low-pressure low-power startup condition has been studied numerically (using RELAP5) and compared with its scaled model.
S. P. Lakshmanan, Manmohan Pandey
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Improved technique of a complex analysis of crack resistance of WWER-1000 nuclear reactor cold leg nozzle under termal shock. Report 1. Thermo-hydraulic and transient thermal calculations [PDF]
, 2014 В Україні для тепло-гідравлічних розрахунків різних сценаріїв, можливих на реакторних установках АЕС,використається розрахунковий комплекс RELAP5. Проблема полягає в тім, що розрахунки в RELAP5 звичайно проводять у районі патрубка корпуса реактора на ...
Iakovlev, A. +3 more
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International Journal of Advanced Nuclear Reactor Design and Technology, 2020 Passive safety systems mostly working on the principles of natural circulation are given much priority in increasing the reliability of reactors’ inherent safety features.
Abbati Zahraddeen +4 more
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RELAP5-3D Code Validation for RBMK Phenomena [PDF]
, 1999 The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a ...
openaire +4 more sources
Analisi di un evento di PTS originato da un incidente di tipo MSLB in un impianto nucleare WWER-1000/320 condotta mediante i codici accoppiati Relap5, Trio_U e Ansys [PDF]
, 2003 Titolo della tesi: “Analisi di meccanica della frattura del vessel di un impianto nucleare WWER-1000/320 condotta mediante i codici accoppiati Relap5, Trio_U e Ansys, in caso di un evento di PTS originato da un incidente di tipo MSLB” Riassunto: Il ...
Vettori, Stefano
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Yuanzineng kexue jishuAfter Fukushima nuclear accident, the passive concept is widely adopted in the thermal safety design of advanced nuclear reactors. The in-pool passive residual heat removal system (PRHRS) can also provide security guarantee for the domestic reactor ...
LIAN Qiang1, 2, 3, ZHU Longxiang1, 2, 3, TANG Simiao1, 2, 3, HUANG Tao4, ZHANG Yong4, PAN Liangming1, 2
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