Results 41 to 50 of about 1,137 (200)
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.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 mitigation
, 1995 Neutron irradiation affects the material properties, and hence the structural integrity, of reactor pressure vessels in nuclear power plants. Mitigation of irradiation damage is one of the major issues within nuclear plant life management. An overview is given of proposed and utilized mitigation methods. Low-leakage loading schemes are commonly used in
Pelli, Reijo +3 more
+5 more sources
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
Advanced Electronic Materials, EarlyView.Composite‐based flexible electronics integrate biodegradable polymers, conductive networks, and multilayer device architectures to balance electrical performance, mechanical durability, and controlled degradation. Interfacial engineering and encapsulation regulate transport stability and operational lifetime, while programmed disassembly enables ...
Sayam, Sangho Cho
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
Journal of Applied Polymer Science, EarlyView.Mechanistic insights from additive‐assisted plastic degradation guide the design of environmentally adaptive textile fibers. Functional additives enhance oxidative, hydrolytic, enzymatic, and microbial degradation pathways. Translating these strategies requires control of fiber architecture, additive distribution, and environmental interactions ...
Julia Cunniffe +2 more
wiley +1 more source
Grain size reduction strategies on Eurofer
Nuclear Materials and Energy, 2018 One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled blanket”. This option implies a minimum irradiation temperature for the blanket material in the range of 280–350 °C.
L. Pilloni +4 more
doaj +1 more source