4.7 Article

Evolution of microstructure and mechanical properties of ZrC reinforced FeCrAl alloy after Fe-ions irradiation

相关参考文献

注意:仅列出部分参考文献,下载原文获取全部文献信息。
Article Materials Science, Multidisciplinary

In Situ Micro-Pillar Compression to Examine Radiation-Induced Hardening Mechanisms of FeCrAl Alloys

Yuchi Cui et al.

Summary: The study demonstrates that 5 MeV Fe2+ ion irradiation at 300 degrees C affects the microstructure evolution and deformation behavior of FeCrAl C26M alloy, with dislocation loop density and size increasing with irradiation dose while different crystallographic orientations exhibit variations in slip systems.

ACTA MATERIALIA (2021)

Article Nanoscience & Nanotechnology

Study on high temperature creep behavior of the accident-resistant cladding Fe-13Cr-4Al-1.85Mo-0.85Nb alloy

Hongying Sun et al.

Summary: The study systematically investigates the creep behaviors of a Fe-13Cr-4Al-1.85Mo-0.85Nb alloy at 400-450 degrees C, showing that the steady-state creep rates increase with loaded stress and vary between different directions. The results provide useful references for the engineering application of the alloy as accident-resistant fuel cladding material.

MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2021)

Article Materials Science, Multidisciplinary

Microstructure refinement and mechanical properties improvement in the W-Y2O3 alloys via optimized freeze-drying

Weiqiang Hu et al.

Summary: By optimized freeze-drying and subsequent low temperature sintering, high performance ODS tungsten based alloys were successfully synthesized, with ultrafine grains and high compressive strength.

INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS (2021)

Article Materials Science, Multidisciplinary

Dynamic strain aging behavior of accident tolerance fuel cladding FeCrAl-based alloy for advanced nuclear energy

Yiyong Zhang et al.

Summary: The study investigated the tensile behavior and deformed microstructure of the Fe-13Cr-4Al alloy under different strain rates and temperatures, revealing the occurrence of dynamic strain aging phenomena in the material.

JOURNAL OF MATERIALS SCIENCE (2021)

Article Engineering, Chemical

Fabrication of ultrafine grained FeCrAl-0.6 wt.% ZrC alloys with enhanced mechanical properties by spark plasma sintering

Haiyi Wan et al.

Summary: FeCrAl-0.6 wt.% ZrC alloy with excellent mechanical properties was successfully fabricated by mechanical milling and spark plasma sintering, showing improved tensile strength, percentage elongation, and hardness at high temperatures. The dispersion strengthen by nanosized ZrC and ultra-fine grained structure induced by the milling process were key factors contributing to the alloy's superior mechanical properties.

ADVANCED POWDER TECHNOLOGY (2021)

Article Chemistry, Physical

Evolution of microstructure and mechanical properties of 9Cr ferrite/martensite steels with different Si content after long-term aging at 550 °C

Yiyong Zhang et al.

Summary: In this study, four 9Cr ferrite/martensite (F/M) heat resistant steels with different Si content were developed for advanced Generation IV lead-cooled fast reactor (LFR) fuel cladding materials. Long-term thermal aging at 550 degrees C showed high thermal stability of microstructures in all four steels, with the precipitation of a new Fe2W-type Laves phase after 5000 h aging. The addition of silicon (Si) up to 0.7% exhibited solid solution strengthening effect without detrimental impact on the mechanical properties of the steels studied.

JOURNAL OF ALLOYS AND COMPOUNDS (2021)

Article Materials Science, Multidisciplinary

Characterization of 14Cr ODS Steel Fabricated by Spark Plasma Sintering

Qian Zhao et al.

METALS (2019)

Article Materials Science, Multidisciplinary

Development of accident tolerant FeCrAl-ODS steels utilizing Ce-oxide particles dispersion

Hiroki Shibata et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Radiation-accelerated precipitation in Fe-Cr alloys

Frederic Soisson et al.

ACTA MATERIALIA (2016)

Article Materials Science, Multidisciplinary

Evaluation of hardening behaviors in ion-irradiated Fe-9Cr and Fe-20Cr alloys by nanoindentation technique

Shilei Li et al.

JOURNAL OF NUCLEAR MATERIALS (2016)

Article Nuclear Science & Technology

Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

Bo Cheng et al.

NUCLEAR ENGINEERING AND TECHNOLOGY (2016)

Article Nanoscience & Nanotechnology

Irradiation-enhanced α′ precipitation in model FeCrAl alloys

P. D. Edmondson et al.

SCRIPTA MATERIALIA (2016)

Article Microscopy

Towards an accurate volume reconstruction in atom probe tomography

Daniel Beinke et al.

ULTRAMICROSCOPY (2016)

Article Nuclear Science & Technology

Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors

Nathan Michael George et al.

ANNALS OF NUCLEAR ENERGY (2015)

Article Materials Science, Multidisciplinary

A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment

Dong Jun Park et al.

CORROSION SCIENCE (2015)

Article Materials Science, Multidisciplinary

Nanoindentation on V-4Ti alloy irradiated by H and He ions

Yitao Yang et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

Article Materials Science, Multidisciplinary

Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys

Kevin G. Field et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

Article Materials Science, Multidisciplinary

Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel

Zhangbo Li et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

Article Materials Science, Multidisciplinary

Evaluation of radiation hardening in ion-irradiated Fe based alloys by nanoindentation

Xiangbing Liu et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Evaluation of irradiation hardening of ion-irradiated V-4Cr-4Ti and V-4Cr-4Ti-0.15Y alloys by nanoindentation techniques

Takeshi Miyazawa et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Deformation behavior of laser welds in high temperature oxidation resistant Fe-Cr-Al alloys for fuel cladding applications

Kevin G. Field et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Microstructural changes in a neutron-irradiated Fe-6 at.%Cr alloy

Mukesh Bachhav et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Nanoindentation on an oxide dispersion strengthened steel and a ferritic/martensitic steel implanted with He ions

Yitao Yang et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe-Cr model alloys

F. Bergner et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Oxidation resistance in LBE and air and tensile properties of ODS ferritic steels containing Al/Zr elements

R. Gao et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

K. A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction

M. T. Farmer et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Instruments & Instrumentation

Study on the mechanical properties evolution of A508-3 steel under proton irradiation

Lei Jing et al.

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2014)

Article Materials Science, Multidisciplinary

Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure

Kurt A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2013)

Article Materials Science, Multidisciplinary

Issues to consider using nano indentation on shallow ion beam irradiated materials

Peter Hosemann et al.

JOURNAL OF NUCLEAR MATERIALS (2012)

Article Nuclear Science & Technology

A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques

Ryuta Kasada et al.

FUSION ENGINEERING AND DESIGN (2011)

Editorial Material Multidisciplinary Sciences

Controlling Radiation Damage

Graeme Ackland

SCIENCE (2010)

Article Materials Science, Multidisciplinary

Effect of Cr on the mechanical properties and microstructure of Fe-Cr model alloys after n-irradiation

M. Madjasevic et al.

JOURNAL OF NUCLEAR MATERIALS (2008)

Article Materials Science, Multidisciplinary

Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

K. Yutani et al.

JOURNAL OF NUCLEAR MATERIALS (2007)

Article Materials Science, Multidisciplinary

Effect of heat treatment on the microstructure and corrosion resistance of a Zr-Sn-Nb-Fe-Cr alloy

WQ Liu et al.

JOURNAL OF NUCLEAR MATERIALS (2005)

Article Microscopy

Strategies for fabricating atom probe specimens with a dual beam FIB

MK Miller et al.

ULTRAMICROSCOPY (2005)

Article Biochemistry & Molecular Biology

Theoretical Calculation of Absolute Radii of Atoms and Ions. Part 1. The Atomic Radii

Dulal C. Ghosh et al.

INTERNATIONAL JOURNAL OF MOLECULAR SCIENCES (2002)

Article Physics, Applied

Trajectory overlaps and local magnification in three-dimensional atom probe

F Vurpillot et al.

APPLIED PHYSICS LETTERS (2000)