Mechanism study of brittle-to-ductile transition temperature in W-0.2 wt% Al2O3 alloy
W-0.2 wt% Al2O3 alloy plates were fabricated using composite powders prepared by the wet chemical method, followed by cold isostatic pressing, vacuum sintering, and hot-rolling.
Ziwen Zhao +9 more
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Effect of Neutron Fluence Rate on Irradiation Embrittlement of Low-copper RPV Steel
The reactor pressure vessels (RPVs) of pressurized water reactor (PWR) nuclear power plants currently in operation and under construction in China are all made of low-alloy ferritic steels obtained by quenching and tempering treatments (which meet the ...
WU Yazhen, LI Guoyun, WANG Haidong, HUANG Juan, ZHANG Haisheng, SUN Kai, LEI Yang, ZHU Lini
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Anti-Oxidation Agents to Prevent Dye Degradation in Organic-Based Host-Guest Systems Suitable for Luminescent Solar Concentrators. [PDF]
Villafiorita-Monteleone F +2 more
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This paper addresses the significant requirements in China's fusion engineering and investigates the preparation technology and performance characterization of high-performance tungsten-based materials used as PFMs.
Gang Yao +6 more
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DBTT measurement by use of small punch(SP) test
微小試験片による延性脆性遷移温度(DBTT)の評価法について、スモールパンチ(SP)試験を中心に検討を行った。熱時効、冷間加工、中性子照射を行った21/4Cr-1Mo鋼及び鉄基モデル合金を用い、SP試験によるDBTT評価の課題を検討した結果、SPによるDBTTとシャルピー試験によるDBTTは全般的には良い相関が得られた。しかしながら、粒界脆化型のDBTTの上昇に関しては、SP試験片の破壊破面観察等を組み合わせることにより、脆化のより的確な判断を行っていく必要があることが判った。
openaire
Thermo-Mechanical Processing as Method Decreasing Delta-Ferrite and Improving the Impact Toughness of the Novel 12% Cr Steels with Low N and High B Contents. [PDF]
Fedoseeva A, Dolzhenko A, Kaibyshev R.
europepmc +1 more source
Effect of Delamination and Grain Refinement on Fracture Energy of Ultrafine-Grained Steel Determined Using an Instrumented Charpy Impact Test. [PDF]
Inoue T, Kimura Y.
europepmc +1 more source
Relative mobility of screw versus edge dislocations controls the ductile-to-brittle transition in metals. [PDF]
Lu Y, Zhang YH, Ma E, Han WZ.
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Radiation damage in tungsten under high-energy He-ion irradiation
Tungsten (W) is a primary candidate for plasma-facing components (PFCs) in fusion reactors and hybrid fission-fusion reactors. However, W suffers from severe microstructural damage under Helium (He) ion irradiation in operation conditions.
Yinghang Liu +10 more
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