Results 31 to 40 of about 848 (238)

Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents

open access: yesNuclear Engineering and Technology, 2023
The core catcher is used as a passive safety system in new generation nuclear power plants to create a space in the containment for the placing and cooling of the molten corium under various severe accidents.
Farhad Salari   +2 more
doaj   +1 more source

Recent Advances in Ferrite‐Based Materials for Biomedical Applications: A Comprehensive Review

open access: yesAdvanced Materials, EarlyView.
Ferrite nanoplatforms are presented as tunable biomedical materials in which synthesis control, cation engineering, defect/morphology regulation, and surface functionalization govern structure–property–bioactivity relationships. These design strategies enable multifunctional applications including MRI contrast, magnetic hyperthermia, targeted drug ...
Pramod D. Mhase   +6 more
wiley   +1 more source

Intelligent Maintenance Review for Robots: Multimodal Information, Deep Diagnosis and Embodied Artificial Intelligence

open access: yesAdvanced Robotics Research, EarlyView.
This review maps the methods to monitor robots’ health by fusing vibration, sound, control signals, vision, force, and oil information with artificial intelligence. It identifies deep learning, transfer learning, digital twins, and physics‐informed models as key methodological pathways enabling earlier diagnosis, safer human–robot collaboration, and ...
Yuting Qiao   +6 more
wiley   +1 more source

Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors

open access: yesNuclear Engineering and Technology
The passive safety systems (PSSs) within water-cooled reactors are meticulously engineered to function autonomously, requiring no external power source or manual intervention.
Hossam H. Abdellatif   +3 more
doaj   +1 more source

Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5

open access: yesJournal of Nuclear Engineering, 2021
The safety performance of nuclear power plants (NPPs) is a very important factor in evaluating nuclear energy sustainability. Safety analysis of passive and active safety systems have a positive influence on reactor transient mitigation.
Fabiano Gibson Daud Thulu   +2 more
doaj   +1 more source

Fundamentals of Thermal Transport and Energy Conversion in Ultra‐High Temperature Ceramics: From Microscale Mechanisms to Macroscopic Properties

open access: yesAdvanced Science, EarlyView.
This review critically examines thermal transport and radiative properties of ultra‐high temperature ceramics for hypersonic flight, advanced nuclear systems, and next‐generation energy conversion devices. It explores phonon–photon–electron interactions, microstructural engineering, thermoelectric conversion, and machine learning‐accelerated multiscale
Zhipeng Pei   +8 more
wiley   +1 more source

Real-time estimation of break sizes during LOCA in nuclear power plants using NARX neural network

open access: yesNuclear Engineering and Technology, 2019
This paper deals with break size estimation of loss of coolant accidents (LOCA) using a nonlinear autoregressive with exogenous inputs (NARX) neural network.
Mahdi Saghafi, Mohammad B. Ghofrani
doaj   +1 more source

Study on Typical Design Basis Conditions of HPR1000 With Nuclear Safety Analysis Code ATHLET

open access: yesFrontiers in Energy Research, 2020
The third-generation nuclear power plant Hua-long Pressurized Reactor (HPR1000) is developed based on the experience of Chinese commercial Nuclear Power Plant (NPP) designs, construction, operation and maintenance.
Xi Huang   +6 more
doaj   +1 more source

Closed‐Loop Radiative Cooling Mulch Upcycled From Agricultural Residues for Efficient Soil Heat–Water Stress Mitigation

open access: yesAdvanced Science, EarlyView.
Conventional passive radiative cooling films rely on costly feedstocks and energy‐intensive fabrication, with poor end‐of‐life compatibility in agriculture. To address this challenge, a sustainable radiative cooling mulch (SRCM) is developed from waste maize leaves via spontaneous hydrogen‐bond self‐assembly.
Hao Li   +13 more
wiley   +1 more source

Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident

open access: yesScience and Technology of Nuclear Installations, 2021
Floating nuclear power plant is a kind of nuclear power plant on a barge moored specifically in an area of the sea. In order to study the factors influencing airborne radionuclide dispersion induced by the loss-of-coolant accident in floating nuclear ...
Shuliang Zou, Na Liu, Binhai Huang
doaj   +1 more source

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