Results 1 to 10 of about 2,651,698 (166)
Alexandria Engineering Journal, 2018 Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar +3 more
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Nuclear Engineering and Technology, 2018 An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with ...
Takeshi Takeda
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RELAP5/MOD3.3 Code Validation with Plant Abnormal Event [PDF]
Science and Technology of Nuclear Installations, 2008 Measured plant data from various abnormal events are of great importance for code validation. The purpose of the study was to validate the RELAP5/MOD3.3 Patch 03 computer code with the abnormal event which occurred at Krško Nuclear Power Plant (NPP) on ...
Andrej Prošek, Borut Mavko
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Nuclear Engineering and Technology, 2018 An experiment was performed using the large-scale test facility (LSTF), which simulated a 1% vessel upper head small-break loss-of-coolant accident with an accident management (AM) measure under an assumption of total-failure of high-pressure injection ...
Takeshi Takeda
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MNSR transient analysis using the RELAP5/Mod3.2 code
Nuclear Engineering and Technology, 2020 To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated.
S. Dawahra, K. Khattab, F. Alhabit
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Nukleonika, 2015 The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear reactor. The aim of the paper is to describe the phenomena and calculate thermal-hydraulic characteristic parameters in the fuel assembly for a European ...
Skrzypek Maciej, Laskowski R.
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Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code
Science and Technology of Nuclear Installations, 2015 Cases of core coolant flow blockage transient have been simulated and analysed for the TRIGA IPR-R1 research reactor using the RELAP5-MOD3.3 code. The transients are related to partial and to total obstruction of the core coolant channels.
Patrícia A. L. Reis +4 more
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Energies, 2021 In-box LOCA was identified as one of the worst accidental scenarios for the HCLL TBS (Helium Cooled Lithium-Lead Test Blanket System). Aiming to experimentally analyze the consequences of this transient, ENEA designed and built THALLIUM (Test HAmmer in ...
Alessandro Venturini +2 more
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RELAP5 application for water hammer analysis in different thermal-hydraulic systems
International Journal of Thermofluids, 2022 The water hammer phenomenon investigations employing RELAP5 code with one-dimensional two-fluid six-equation models of water and steam flow were performed and the main results shared in this paper.
Algirdas Kaliatka +3 more
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Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor [PDF]
Nuclear Technology and Radiation Protection, 2006 RELAP5 is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants.
Bousbia-Salah Anis +5 more
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