Results 41 to 50 of about 1,033,988 (155)
Steam generator performance improvements for integral small modular reactors
Nuclear Engineering and Technology, 2017 Background: Steam generator (SG) is one of the significant components in the nuclear steam supply system. A variety of SGs have been designed and used in nuclear reactor systems. Every SG has advantages and disadvantages.
Muhammad Ilyas, Fatih Aydogan
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.In the design of nuclear power plant systems, the thermal–hydraulic response in the containment during a loss‐of‐coolant accident (LOCA) plays a crucial role. In this study, the advanced small modular reactor NHR200‐II is selected as the research object.
Yan Wang +3 more
wiley +1 more source
STH‐CFD Codes Coupled Calculations Applied to HLM Loop and Pool Systems
Science and Technology of Nuclear Installations, Volume 2017, Issue 1, 2017., 2017 This work describes the coupling methodology between a modified version of RELAP5/Mod3.3 and ANSYS Fluent CFD code developed at the University of Pisa. The described coupling procedure can be classified as “two‐way,” nonoverlapping, “online” coupling. In this work, a semi‐implicit numerical scheme has been implemented, giving greater stability to the ...
M. Angelucci +5 more
wiley +1 more source
Recent Applications of RELAP5-3D at GRNSPG [PDF]
, 2012 CNA2 : FSAR activities Standard Consolidated Reference Experimental Database MASLWR benchmark OECD benchmarks CHF calculation in low mass flux condition Turbulence effects in Relap5 ...
Veronese, F. +9 more
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[Logiciel] Open source 3D viewer
, 2021 "Voyager is part of the Smithsonian’s Digitization Program Office’s 3D foundation pipeline.
Consortium 3D SHS Team
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Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP
Science and Technology of Nuclear Installations, 2015 This paper presents the results of the analysis of the Unprotected Loss of Flow (ULOF) experiment SHRT-45R performed in the EBR-II fast reactor. These experiments are being analyzed in the scope of a benchmark exercise coordinated by the IAEA.
W. F. G. van Rooijen, H. Mochizuki
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.Sodium‐cooled fast reactor (SFR) is one of the fourth‐generation nuclear reactor types, which has inherent safety features such as low corrosion and no severe interaction between molten fuel and sodium. However, the severe accident of core melting in SFR needs to be considered.
Yingying Huo +3 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2017, Issue 1, 2017., 2017 A core catcher has been developed to maintain the integrity of nuclear reactor containment from molten corium during a severe accident. It uses a two‐phase natural circulation for cooling molten corium. Flow in a typical core catcher is unique because (i) it has an inclined cooling channel with downwards‐facing heating surface, of which flow processes ...
Dong Hun Lee +5 more
wiley +1 more source
, 2001 The Reactor Excursion and Leak Analysis Program with 3D capability1 (RELAP5-3D) is a reactor system analysis code that has been developed at the Idaho National Engineering and Environmental Laboratory (INEEL) for the U. S. Department of Energy (DOE). The
Riemke, Richard Allan
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International Journal of Energy Research, Volume 2025, Issue 1, 2025.Increased energy supply reliability, environmental sustainability, more competitive businesses, and improved standard of living are all made possible by more efficient energy conversion processes. In view of this, the present study aims at analysis and optimization of the operational parameters of a dual‐fuel‐fired boiler using Taguchi design method to
Sunday O. Oyedepo +5 more
wiley +1 more source