Results 81 to 90 of about 5,521 (168)
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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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
Analisis Perbandingan Kinerja Perangkat Bahan Bakar Pltn Tipe Pwr Ap 1000 Dan Pwr 1000 Mwe Tipikal Dengan Menggunakan Program Komputer [PDF]
, 2014 Investigation of fuel element thermal-hydraulic characteristic is important step related to aspect of fuel bundle reactor design. This paper analyzes of the PWR AP1000 and PWR 1000 MWe Typical of fuel bundle thermal-hydraulic using RELAP5 code.
Nurmawan, A. (Arif) +2 more
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Science and Technology of Nuclear Installations, 2016 The latest versions of RELAP5-3D© code allow the simulation of thermodynamic system, using different type of working fluids, that is, liquid metals, molten salt, diathermic oil, and so forth, thanks to the ATHENA code integration.
P. Balestra +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
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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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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Science and Technology of Nuclear Installations, 2015 RELAP5 is a system thermal-hydraulic code that is used to perform safety analysis on nuclear reactors. Since the code is based on steady state, two-phase flow regime maps, there is a concern that RELAP5 may provide significant errors for rapid transient ...
Viet-Anh Phung +3 more
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