Recent progress in understanding reactor pressure vessel steel embrittlement
GR Odette, GE Lucas - Radiation effects and defects in solids, 1998 - Taylor & Francis
This paper reviews the current understanding of the basic mechanisms of irradiation
embrittlement in reactor pressure vessel steels. Radiation enhanced diffusiona at operating …
embrittlement in reactor pressure vessel steels. Radiation enhanced diffusiona at operating …
The influence of helium on the bulk properties of fusion reactor structural materials
H Ullmaier - Nuclear fusion, 1984 - iopscience.iop.org
Radiation-induced deterioration of fission reactor materials is dominated by displacement
damage. In fusion reactors, the influence of (n, α) produced helium upon material …
damage. In fusion reactors, the influence of (n, α) produced helium upon material …
Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation
In recent years, high entropy alloys (HEAs) have attracted significant attention due to their
excellent mechanical properties and good corrosion resistance, making them potential …
excellent mechanical properties and good corrosion resistance, making them potential …
Materials challenges in nuclear energy
Nuclear power currently provides about 13% of electrical power worldwide, and has
emerged as a reliable baseload source of electricity. A number of materials challenges must …
emerged as a reliable baseload source of electricity. A number of materials challenges must …
[图书][B] Fundamentals of Radiation Materials Science: Metals and Alloys
GS Was - 2007 - books.google.com
The revised second edition of this established text offers readers a significantly expanded
introduction to the effects of radiation on metals and alloys. It describes the various …
introduction to the effects of radiation on metals and alloys. It describes the various …
High-chromium ferritic and martensitic steels for nuclear applications
RL Klueh, DR Harries - 2001 - asmedigitalcollection.asme.org
Untitled Page 1 Page 2 High-Chromium Ferritic and Martensitic Steels for Nuclear Applications
Ronald L. Klueh and Donald R. Harries ASTM Stock Number: MONO3 ASTM 100 Barr Harbor …
Ronald L. Klueh and Donald R. Harries ASTM Stock Number: MONO3 ASTM 100 Barr Harbor …
Fracture toughness of type 304 and 316 stainless steels and their welds
WJ Mills - International Materials Reviews, 1997 - journals.sagepub.com
Fracture toughness data for type 304 and 316 stainless steels and their welds are reviewed.
The material and operational parameters evaluated in this paper include: heat to heat …
The material and operational parameters evaluated in this paper include: heat to heat …
Analysis of displacement damage and defect production under cascade damage conditions
SJ Zinkle, BN Singh - Journal of nuclear materials, 1993 - Elsevier
The production, annihilation, and accumulation of point defects in metals during displacive
irradiation is dependent on a variety of physical conditions, including the nature and energy …
irradiation is dependent on a variety of physical conditions, including the nature and energy …
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys
The RIS mechanism in austenitic and ferritic–martensitic (F–M) alloys is addressed by both
atomic-scale modeling and experiment. Ab initio based modeling shows that the inverse …
atomic-scale modeling and experiment. Ab initio based modeling shows that the inverse …
Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments
Nuclear energy provides more than 10% of electrical power internationally and the
increasing engagement of nuclear energy is essential to meet the rapid worldwide increase …
increasing engagement of nuclear energy is essential to meet the rapid worldwide increase …