Results 61 to 70 of about 1,645 (179)

Density Functional Theory‐Based Investigation of Adsorption, Permeation, and Desorption of Hydrogen Isotopes in Fe–Cr Alloy of Varied Compositions

ChemPhysChem, Volume 27, Issue 14, 29 July 2026.
The energy profile of H from tetrahedral to a nearby tetrahedral void is changed with changes in Cr content. The diffusion coefficients of H are also found to vary with variation in the Cr content in the Fe–Cr alloy. These changes in energy and diffusion are due to the altered electronic interaction of hydrogen within the alloy matrix with varying Cr ...
Anil Boda, Sk. MusharafAli
wiley   +1 more source

Template‐Assisted 3D‐PVDF Nanonetworks for Passive Daytime Radiative Cooling

Nanophotonics, Volume 15, Issue 13, 13 July 2026.
Three‐dimensional polyvinylidene fluoride (3D‐PVDF) nanostructures were fabricated by infiltrating the polymer into 3D anodic aluminum oxide (3D‐AAO) templates. Due to their high solar reflectance (82.4%) and infrared emissivity (96.7% between 8 and 13 µm), they are an ideal candidate for radiative cooling.
Amaia Iglesias‐Elcano, Luis Moreno‐Sanabria, Marisol Martín‐González, Cristina V. Manzano   +3 more
wiley   +1 more source

Properties of W–Ta Materials of the Neutron-Producing Target of the Subcritical Assembly at the National Scientific Centre ‘Kharkiv Institute of Physics and Technology’ of the National Academy of Sciences of Ukraine

Успехи физики металлов
The works in the field of radiation materials science of target materials of neutron sources based on the subcritical assemblies controlled by linear accelerators of electrons or protons, so-called accelerator driven systems (ADS), are reviewed.
B.V. Borts, O.O. Parkhomenko, V.V. Gann, A.Yu. Zelinsky, V.I. Sytin, I.O. Vorobyov, L.I. Gluschenko, I.I. Karnaukhov, Yu.O. Marchenko, and M.P. Domnich
doaj   +1 more source

Tensile properties of EUROFER97-3 after neutron irradiation at 330 °C and 540 °C to damage doses of 19–23 dpa

Nuclear Materials and Energy
The reduced activation ferritic-martensitic (RAFM) EUROFER97-3 steel of two heat treatments (EUROFER97-3_1100/700 and EUROFER97-3_980/780) after irradiation in the BOR-60 fast reactor at temperatures of 330 °C and 540 °C, with damage doses ranging from ...
Vladimir Chakin, Carsten Bonnekoh, Ramil Gaisin, Rainer Ziegler, Michael Duerrschnabel, Michael Klimenkov, Bronislava Gorr, Michael Rieth   +7 more
doaj   +1 more source

Rupture Process of the 26 May 2019 Mw 8.0 Northern Peru Intermediate‐Depth Earthquake and Insights Into Its Mechanism

Geophysical Research Letters, 2020
In the Nazca‐South American subduction zone, the subducted slab is flattened beneath northern Andes, called the Peruvian flat slab. The 2019 Mw 8.0 northern Peru intermediate‐depth normal‐faulting earthquake occurred at the leading edge of the Peruvian ...
Wei Liu, Huajian Yao
doaj   +1 more source

Analysis of dpa Rates in the HFIR Reactor Vessel using a Hybrid Monte Carlo/Deterministic Method*

EPJ Web of Conferences, 2016
The Oak Ridge High Flux Isotope Reactor (HFIR), which began full-power operation in 1966, provides one of the highest steady-state neutron flux levels of any research reactor in the world.
Risner J.M., Blakeman E.D.
doaj   +1 more source

Development and Validation of Radiation Embrittlement Prediction Model of Austenitic Stainless Steel

Yuanzineng kexue jishu
Austenitic stainless steels are used as important structural materials in nuclear reactors due to their high fracture toughness. In the process of long-term service, austenitic stainless steel will be subjected to neutron irradiation to cause ...
JIA Lixia, WANG Dongjie, HE Xinfu, WU Shi, YANG Wen
doaj   +1 more source

The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

Frontiers in Nuclear Engineering
It is necessary to quantify the effects of flux on reactor pressure vessel steel embrittlement under neutron irradiation, if surveillance or high-flux test reactor data is used to predict vessel embrittlement occurring at lower fluxes.
Susan Ortner, Paul Styman, Elliot Long
doaj   +1 more source

First-principles study on hydrogen segregation in tungsten grain boundaries and its impact on their mechanical strengths: Uniaxial tensile strain effect

Nuclear Materials and Energy
Based on comprehensive first-principles calculations, this study systematically investigates hydrogen (H) segregation behavior at Σ3(112)[110] and Σ5(310)[100] tungsten (W) grain boundaries (GBs) under uniaxial tensile strain, and its consequent impact ...
Quan-Fu Han, Jinxin Chen, Aoyu Mo, Wenjie Li, Haijun Li, Xiaowei Ma, Yunshan Xiong, Peng Shao, Bo Li, Kun Jie Yang, Yue-Lin Liu   +10 more
doaj   +1 more source

Radiation Damage Exposure and Embrittlement of Reactor Pressure Vessels

Nuclear Applications, 1966
A radiation damage model that accounts for neutron spectral differences between irradiation locations has been applied to pertinent data on the change in ductile-to-brittle transition temperature f...
openaire   +2 more sources