Results 11 to 20 of about 280 (176)
Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction
Science and Technology of Nuclear Installations, 2022 The gravity cooling water tank is a remarkable structural feature of third-generation pressurized water reactor nuclear power plant. To investigate the influence of fluid-structure interaction (FSI) on the seismic response of the structure, this study ...
Zhi Zhang +3 more
doaj +2 more sources
Science and Technology of Nuclear InstallationsOn September 2021, Polish government declared that six pressurized water reactors with combined capacity of 6–9 GWe will be built by 2040 to reduce Poland’s reliance on coal. Due to the adopted schedule, construction of the first nuclear power plant will
Edyta Agata Macieja, Juyoul Kim
doaj +2 more sources
Topography-Free Dual-Lubricant Patterned Slippery Surfaces for Programmable Droplet Control and High-Performance Water Harvesting. [PDF]
SmallA patterned dual‐lubricant SLIPS creates interfacial energy asymmetry, guiding droplet migration without external actuation. Condensed droplets formed on the fluorinated‐oil‐infused regions migrate to the silicone‐oil‐infused domains, where rapid growth and coalescence occur.
Yang J +11 more
europepmc +2 more sources
Optimization and performance of metafoundations for seismic isolation of small modular reactors
Computer-Aided Civil and Infrastructure Engineering, Volume 38, Issue 12, Page 1558-1582, August 2023., 2023 Abstract This paper aims to study the seismic mitigation of a typical nuclear small modular reactor (SMR) where extreme loading conditions are considered by the safe shutdown earthquake. For this purpose, to reproduce the main dynamic properties of the reactor's reinforced concrete system, a detailed structural model was synthetized, also taking into ...
Tugberk Guner +2 more
wiley +1 more source
International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023 The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in‐vessel melt retention, one requires high‐fidelity predictions on the natural circulation flow around the reactor vessel and, in ...
Yeon-Gun Lee, Il Woong Park, Geng Chen
wiley +1 more source
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland
Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023 This paper introduces the utilization of the International Atomic Energy Agency’s toolkit for reactor technology assessment (RTA) application to deploy small modular reactors (SMRs) in the Czech Republic, Egypt, and Poland. The increasing demand for clean energy has led to the prominence of small modular reactors (SMRs) in addressing global energy ...
Waad Saleh +4 more
wiley +1 more source
Research on the sneak circuit analysis method of a thermal system based on energy flow
Energy Science &Engineering, Volume 10, Issue 9, Page 3358-3370, September 2022., 2022 Convert the heat accumulator to an energy flow model. Sneak circuit analysis of thermal system based on improved energy flow method. Analyze sneak paths of thermal systems with different types of heat accumulators. Abstract Based on the energy flow analysis method, this paper establishes the relationship between the heat accumulator and the thermal ...
Xiaoyu Shen +4 more
wiley +1 more source
Nanoparticle Internalization Promotes the Survival of Primary Macrophages
Advanced NanoBiomed Research, Volume 2, Issue 5, May 2022., 2022 Nanoparticle (NP) treatment to macrophages causes enhanced ex vivo survival following a single dose. NP phagocytosis triggers lysosomal signaling, which promotes prosurvival factors and suppresses proapoptotic pathways. NP‐induced survival occurs in the absence of aberrant inflammatory effects.
Bader M. Jarai, Catherine A. Fromen
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The micro‐mechanical state at the crack front is one of the key factors affecting the stress corrosion cracking (SCC) growth behavior. The mechanical heterogeneity and residual stress in the dissimilar metal welded joint (DMWJ) induce the micro‐mechanical state at the crack front to become more complex.
Shun Zhang +5 more
wiley +1 more source
Fault Diagnosis to Nuclear Power Plant System Based on Time‐Series Convolution Neural Network
Wireless Communications and Mobile Computing, Volume 2022, Issue 1, 2022., 2022 Nuclear power plant (NPP) is a highly complex engineering system which has typical internal feedback and strong component coupling. With these features, most NPP systems have high risk of radioactive release, which makes it essential to perform fault detection (FD) to the NPP systems.
XianLing Li +7 more
wiley +1 more source