Results 71 to 80 of about 1,865 (177)
Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB
Energies, 2021 The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design of the WCLL-BB (water-cooled lead-lithium breeding blanket).
Marica Eboli +5 more
doaj +1 more source
International Journal of Energy Research, Volume 2024, Issue 1, 2024.In the case of multiple‐failure accidents in light water reactors, it is imperative to demonstrate that a significant fuel damage can be prevented via prearranged mitigation measures performed by operators. However, the time elapsed from the initiation of the event to the implementation of mitigation actions significantly influences the progress and ...
Jia Yu +3 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.
core
Yuanzineng kexue jishuAfter Fukushima nuclear accident, the passive concept is widely adopted in the thermal safety design of advanced nuclear reactors. The in-pool passive residual heat removal system (PRHRS) can also provide security guarantee for the domestic reactor ...
LIAN Qiang1, 2, 3, ZHU Longxiang1, 2, 3, TANG Simiao1, 2, 3, HUANG Tao4, ZHANG Yong4, PAN Liangming1, 2
doaj +1 more source
Core Flow Distribution from Coupled Supercritical Water Reactor Analysis
Science and Technology of Nuclear Installations, 2014 This paper introduces an extended code package PARCS/RELAP5 to analyze steady state of SCWR US reference design. An 8 × 8 quarter core model in PARCS and a reactor core model in RELAP5 are used to study the core flow distribution under various steady ...
Po Hu, Paul P. H. Wilson
doaj +1 more source
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
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
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
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.
core