Results 11 to 20 of about 5,558 (186)
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
doaj +3 more sources
Energies, 2021 Magnetohydrodynamic (MHD) phenomena, due to the interaction between a magnetic field and a moving electro-conductive fluid, are crucial for the design of magnetic-confinement fusion reactors and, specifically, for the design of the breeding blanket ...
Vincenzo Narcisi +2 more
exaly +3 more sources
Burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1 [PDF]
Nuclear Technology and Radiation Protection, 2011 The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, reference operating core, has been carried out utilizing standard computer codes WIMS/D4, CITATION, and RELAP5/MOD3.4.
Muhammad Atta +2 more
doaj +3 more sources
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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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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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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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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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
doaj +1 more source
Study on the Density Wave Instability in Natural Circulation System under Rolling Conditions
International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023 In the ocean environment, the thermal fluid system installed on the ship moves with the waves. This unsteady transient motion imposes additional body forces on the liquid. Thereby, the thermohydraulic properties of the thermal fluid system are changed, especially for natural circulation systems with a low driving force.
Houjun Gong +6 more
wiley +1 more source