Results 71 to 80 of about 2,651,698 (166)
Analysis of Loss of Flow Events on Brazilian Multipurpose Reactor Using the Relap5 Code
, 2014 This work presents the thermal hydraulic simulation of the Brazilian multipurpose reactor (RMB) using a RELAP5/MOD3.3 model. Beyond steady state calculations, three transient cases of loss of flow accident (LOFA) in the primary cooling system have been ...
H. V. Soares +4 more
semanticscholar +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
Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development
Energies, 2021 The present paper describes the experimental campaign executed at the ENEA Brasimone Research Centre aiming at supporting the development of a PbLi/water heat exchanger suitable for the lithium–lead loops of the dual coolant lithium lead and the water ...
Pierdomenico Lorusso +5 more
doaj +1 more source
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
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
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
Atom Indonesia, 2019 In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident.
A.R. Antariksawan +7 more
doaj +1 more source
EnergiesThe RELAP5 code is a computational tool designed for transient simulations of light water reactor coolant systems under hypothesized accident conditions.
Young Hwan Lee +2 more
doaj +1 more source
Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator
Science and Technology of Nuclear Installations, 2016 Helically coiled tube Once-Through Steam Generator (H-OTSG) is one of the key equipment types for small modular reactors. The flow instability of the secondary side of the H-OTSG is particularly serious, because the working condition is in the range of ...
Junwei Hao +7 more
doaj +1 more source
RELAP5/SIMMER-III code coupling development for PbLi-water interaction
Fusion Engineering and Design, 2020 Abstract A major safety issue in the Water-Cooled Lead-Lithium Breeding Blanket (WCLL-BB) system foreseen for fusion reactor is the interaction concerning the primary coolant (water) and the neutron multiplier (PbLi), due to a hypothetical tube rupture in the coolant circuit.
Galleni F. +7 more
openaire +2 more sources