Results 21 to 30 of about 340 (167)

High-temperature tensile and thermal shock characterization of low-temperature rolled tungsten

Nuclear Materials and Energy, 2023
A developed tungsten (W) grade was prepared by powder metallurgy technology plus multi-step low-temperature rolling. The relative density, thermal conductivity, microstructure, tensile properties of original and high-temperature annealed states, micro ...
Xiaolei Ma, Xiaoxin Zhang, Fan Feng, Ting Wang, Xiang Liu, Jianbao Wang, Wei Lv, Shaoting Lang, Changchun Ge, Qingzhi Yan   +9 more
doaj   +1 more source

Effects of thermal aging at 873 K on the impact properties of an ODS ferritic steel

Nuclear Materials and Energy, 2023
This investigation presents the effects of long-term thermal aging on the impact properties of an ODS reduced activation ferritic steel. The ODS ferritic steel, with composition Fe–14Cr–2W–0.4Ti–0.3Y2O3 (wt.
M. Oñoro, T. Leguey, V. de Castro, M.A. Auger   +3 more
doaj   +1 more source

Microstructural Features and Ductile-Brittle Transition Behavior in Hot-Rolled Lean Duplex Stainless Steels

Quantum Beam Science, 2020
The characteristics of texture and microstructure of lean duplex stainless steels with low Ni content produced through hot rolling followed by annealing were investigated locally with electron backscatter diffraction and globally with neutron diffraction.
O. Takahashi, Y. Shibui, P.G. Xu, S. Harjo, T. Suzuki, Y. Tomota   +5 more
doaj   +1 more source

Effects of Orthogonal Heat Treatment on Microstructure and Mechanical Properties of GN9 Ferritic/Martensitic Steel

Chinese Journal of Mechanical Engineering, 2023
Microstructure and mechanical properties of GN9 Ferritic/Martensitic steel for sodium- cooled fast reactors have been investigated through orthogonal design and analysis.
Tingwei Ma, Xianchao Hao, Ping Wang
doaj   +1 more source

Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon content

Nuclear Materials and Energy, 2021
In this work, we investigate an alternative route for the production of reduced activation ferritic-martensitic (RAFM) steels with reduced contents of manganese and carbon.
D. Terentyev, A. Puype, O. Kachko, W. Van Renterghem, J. Henry   +4 more
doaj   +1 more source

Embrittlement of WCLL blanket and its fracture mechanical assessment

Nuclear Fusion, 2023
In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar.
Jarir Aktaa, Ermile Gaganidze, Gaetano Bongioví, Pietro Arena, Gandolfo Alessandro Spagnuolo, Giacomo Aiello, Pierluigi Chiovaro, Christian Bachmann   +7 more
doaj   +1 more source

A Data-driven machine learning model for radiation-induced DBTT shifts in RAFM steels

Journal of Nuclear Materials
Gebril El-Fallah
exaly   +2 more sources

Effect of Texture and Temperature on Strain‐Induced Martensitic Transformation in 304 Austenitic Stainless Steel

steel research international, Volume 94, Issue 2, February 2023., 2023
The initial crystallographic orientations are changed along with the tensile directions, inducing the difference in mechanical properties and strain‐induced martensitic transformation rate in 304 austenitic stainless steel. Especially, high strength and ductility at both room and cryogenic temperatures are achieved when the material has more volume ...
Jeong-Chan Lee, Yeonju Noh, Nam-Su Kim, Ki Beom Park, Hyunghoon Kim, Hyung-Hwan Cho, Hyung-Ki Park, Tea-Sung Jun, Chang-Soo Park   +8 more
wiley   +1 more source

Effect of Scan Length on Densification and Crystallographic Texture Formation of Pure Chromium Fabricated by Laser Powder Bed Fusion

Crystals, 2020
Processing of pure chromium (Cr) encounters substantial challenges due to its high melting point and intrinsic brittleness. Although laser powder bed fusion processing (LPBF) offers a novel processing approach by reaching the temperature required to melt
Ozkan Gokcekaya, Takuya Ishimoto, Tsubasa Todo, Ryoya Suganuma, Ryo Fukushima, Takayuki Narushima, Takayoshi Nakano   +6 more
doaj   +1 more source

Effect of neutron irradiation on ductility of tungsten foils developed for tungsten-copper laminates

Nuclear Materials and Energy, 2022
Severe plastic deformation of tungsten (W) is known to be an efficient way to reduce its inherently high ductile-to-brittle transition temperature (DBTT), what is essential for its use in components of a fusion reactor.
Aleksandr Zinovev, Dmitry Terentyev, Chih-Cheng Chang, Chao Yin, Alexander Bakaev, Michael Rieth, Philipp Lied, Jens Reiser, Carsten Bonnekoh   +8 more
doaj   +1 more source