Results 61 to 70 of about 1,536,451 (138)
Opposing Mixed Convection Heat Transfer for Turbulent Single‐Phase Flows
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Convection, wherein forced and natural convections are prominent, is known as mixed convection. Specifically, when a forced convection flow is downward, this flow is called opposing flow. The objectives of this study are to gain a comprehensive understanding of opposing flow mixed convection heat transfer and to establish the prediction methodology by ...
Kosuke Motegi +5 more
wiley +1 more source
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA
Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.In this work, a machine learning (ML) metamodel is developed for the time‐series forecasting of a typical nuclear power plant response undergoing a loss of coolant accident (LOCA). The plant model of choice is based on the APR1400 nuclear reactor. The key systems and components of APR1400 relevant to the investigated scenario are modelled using the ...
Michal Kaminski +2 more
wiley +1 more source
Streamlining of the RELAP5-3D Code [PDF]
, 2007 RELAP5-3D is widely used by the nuclear community to simulate general thermal hydraulic systems and has proven to be so versatile that the spectrum of transient two-phase problems that can be analyzed has increased substantially over time. To accommodate
Hykes, Joshua +2 more
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Mathematic preprocessor for RELAP5 code using Microsoft Excel
, 2006 O estudo termo-hidráulico, utilizado para análise de acidentes e transientes em reatores nucleares, é feito com o uso de algumas ferramentas computacionais sofisticadas.
Patricia Andrea Paladino Biaty +1 more
core +1 more source
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Data assimilation (DA) was revealed as a highly efficient approach to enhance the prediction’s accuracy, demonstrating the reliability of the simulation through uncertainty quantification analysis. However, in the numerical simulations, most of the tasks are highly nonlinear relationships between the parameters that directly affect the efficiency of ...
Nguyen Huu Tiep +7 more
wiley +1 more source
RELAP5 code development and assessment at the Savannah River Site [PDF]
, 1991 Over the past year, the focus of RELAP5 use at the Savannah River Site has been on code applications to reactor accidents having a direct bearing on setting power limits, with a lesser emphasis on code development. In the applications task, RELAP5/MOD2.5
Dimenna, R. A.
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Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
Science and Technology of Nuclear Installations, 2008 The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation,
Giacomino Bandini +5 more
doaj +1 more source
Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000
Ядерна фізика та енергетика, 2019 The research presents an analysis of the known results in modeling the maximum design accident (MDA) using the code RELAP5/V3.2 with Westinghouse fuel assemblies’ (WFA) diversification in WWER-1000 reactors.
V. I. Skalozubov +4 more
doaj +1 more source
Peach Bottom turbine-trip Test 3 analysis with RELAP5 code [PDF]
, 1983 The Peach Bottom turbine trip tests provide excellent benchmark problems for transient analysis of a boiling water reactor (BWR). Analyses of the three turbine trip tests with the RELAP3B/BNL-TWIGL, RETRAN and other codes have been documented.
Lu, M.S.
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