Results 1 to 10 of about 5,521 (168)
Advanced Presentation of BETHSY 6.2TC Test Results Calculated by RELAP5 and TRACE [PDF]
Science and Technology of Nuclear Installations, 2012 Today most software applications come with a graphical user interface, including U.S. Nuclear Regulatory Commission TRAC/RELAP Advanced Computational Engine (TRACE) best-estimate reactor system code.
Andrej Prošek, Ovidiu-Adrian Berar
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Transient Analysis of the Flow Behavior under a Small Leakage Accident in Feed Water Pipeline [PDF]
Journal of Applied Fluid Mechanics, 2023 Feedwater leakages due to excessive loads and cracking caused by corrosion or fatigue failure can affect the reliability of the production facilities.
A. Dahia +2 more
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Deterministic analysis of emergency AC power recovery during SB-LOCA along with LOOP accident in Bushehr nuclear power plant [PDF]
مجله علوم و فنون هستهای, 2021 The availability of current AC electrical power is essential for the safe operation and accident recovery of commercial nuclear power plants. Loss of offsite power (LOOP) considers as one of the significant post-Fukushima accidents.
S.A. Hosseini, A.S. Shirani
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Loss of offsite power accident analysis in a VVER-1000/V446 nuclear power plant [PDF]
Nuclear Technology and Radiation Protection, 2019 The aim of this study is to present a thermo-hydraulic analysis of the loss of offsite power accident in VVER-1000/V446 nuclear power plant using the RELAP5 code.
Esfandiari Mohsen +3 more
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RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor
Brazilian Journal of Radiation Sciences, 2021 This work presents the thermal-hydraulic simulation of the Brazilian Multipurpose Reactor (RMB) using the RELAP5/Mod3 code. The RMB will provide Brazil with a fundamental infrastructure for the national development on activities of the nuclear sector in ...
Humberto Vitor Soares +2 more
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He jishu, 2023 BackgroundNuclear power simulation technology has been widely applied in areas such as reactor design, safety analysis, independent safety evaluation, accident mitigation measures, design and optimization of control and protection system, verification of
CHEN Shichao +6 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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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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Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data
Nuclear Engineering and Technology, 2020 We validated the performance of RELAP MOD3.3 code regarding the hybrid SIT with available experimental data. The concept of the hybrid SIT is to connect the pressurizer to SIT to utilize the water inside SIT in the case of SBO or SB-LOCA combined with ...
Ho Joon Yoon +3 more
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