Results 41 to 50 of about 1,250 (204)
Radiative Thermal Management for Extreme Environments: Mechanisms and Design Strategies
Advanced Materials, EarlyView.In this review, we discuss the fundamental mechanisms of radiative cooling and solar heating, material and structural design strategies, hybrid approaches integrating additional heat transfer pathways, and durability‐oriented designs addressing environmental stresses.
Hyung Rae Kim +5 more
wiley +1 more source
Nihon Kikai Gakkai ronbunshu, 2020 The Japan Electric Association code, JEAC 4206-2016 specifies a procedure for assessment of a reactor pressure vessel integrity against pressurized thermal shock (PTS) events which postulates a semi-elliptical flaw (10 mm in depth x 60 mm in length ...
Takatoshi HIROTA +2 more
doaj +1 more source
Analyzing the causes for the dispersion of the fast reactor spent fuel rod cladding properties [PDF]
Nuclear Energy and Technology, 2019 The swelling, corrosion and high-temperature embrittlement behavior of the fast-neutron sodium-cooled reactor standard and test fuel rod claddings was studied following the operation up to a damaging dose of 55 to 69 dpa.
Valeriy N. Shemyakin +5 more
doaj +3 more sources
Feasibility of Safe Operation of WWER-440-Type Nuclear Power Plants for Up to 60–70 Years
Energies, 2023 Most WWER-440 reactors are operated over the planned operational lifetime of 30 years. Now, the owners/operators are preparing for the second phase of extending the operation.
Tamás János Katona +2 more
doaj +1 more source
Advanced Science, EarlyView.This review comprehensively summarizes the atomic defects in TMDs for their applications in sustainable energy storage devices, along with the latest progress in ML methodologies for high‐throughput TEM data analysis, offering insights on how ML‐empowered microscopy facilitates bridging structure–property correlation and inspires knowledge for precise ...
Zheng Luo +6 more
wiley +1 more source
Different approaches to estimation of reactor pressure vessel material embrittlement [PDF]
Ядерна фізика та енергетика, 2013 The surveillance test data for the nuclear power plant which is under operation in Ukraine have been used to estimate WWER-1000 reactor pressure vessel (RPV) material embrittlement.
V. M. Revka +3 more
doaj
Nuclear Materials and Energy, 2023 In this study, a post-irradiation examination of pure tungsten (W) and tantalum (Ta) specimens irradiated at the Swiss Spallation-Neutron Source is conducted.
Shigeru Saito +3 more
doaj +1 more source
Advanced Science, EarlyView.Intrinsic phase toughening transforms a brittle B2 intermetallic into a plastically deformable, load‐bearing phase, while a heterogeneous laminated architecture suppresses strain localization and interface cracking. The synergy between ductile intermetallics and mesoscale heterogeneity establishes a general design strategy for breaking the long ...
Lu Yang +9 more
wiley +1 more source
(Irradiation embrittlement of reactor pressure vessels) [PDF]
, 1990 The traveler served as a member of the two-man US Nuclear Regulatory Commission sponsored team who visited the Prometey Complex in Leningrad to assess the potential for expanded cooperative research concerning integrity of the primary pressure boundary in commercial light-water reactors.
openaire +2 more sources
Advanced Science, EarlyView.This study elucidates the microstructural evolution at the material interface of Ni‐plated plain‐weave carbon fiber fabric following vacuum heat treatment at 500°C–900°C under different current densities, as well as the mechanism underlying the synergistic enhancement of electromagnetic shielding and ductility.
Wei Cheng +7 more
wiley +1 more source