Results 31 to 40 of about 935 (164)

The Role of Water Chemistry for Environmentally Assisted Cracking in Low-Alloy Reactor Pressure Vessel and Piping Steels under Boiling Water Reactor Conditions

open access: yesCHIMIA, 2005
The environmentally assisted initiation and propagation of cracks in structural materials is one of the most important degradation and ageing mechanisms in light water reactors (LWR) and may seriously affect plant availability and economics.
Hans-Peter Seifert, Stefan Ritter
doaj   +1 more source

IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL

open access: yesNuclear Engineering and Technology, 2013
High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core ...
YIREN CHEN
doaj   +1 more source

Influence of irradiation on the dynamics of changes in the mechanical properties of the nuclear reactor vessel

open access: yesMATEC Web of Conferences, 2018
Nuclear power plants are important generating units of the energy system worldwide. In the normal mode, nuclear power plants are absolutely safe, but emergency systems with radiation emissions have a devastating impact on the environment and public ...
Bakhracheva Yulia S.
doaj   +1 more source

Microstructural defects in EUROFER 97 after different neutron irradiation conditions

open access: yesNuclear Materials and Energy, 2016
Characterization of irradiation induced microstructural evolution is essential for assessing the applicability of structural steels like the Reduced Activation Ferritic/Martensitic steel EUROFER 97 in upcoming fusion reactors.
Christian Dethloff   +2 more
doaj   +1 more source

Research progress on composition design and preparation technology of oxide dispersion strengthened steels for advanced nuclear energy systems

open access: yesFenmo yejin jishu
Nuclear energy is a kind of clean energy, developing the Gen IV nuclear energy systems with higher safety and economy is the focus in current research. Traditional zirconium alloys have been unable to adapt to the harsh service environment of the Gen IV ...
ZHAI Yazhong   +3 more
doaj   +1 more source

Dynamic properties of reactor steels Kh16N15M3T1 and Kh13V2 under shock-wave loading of submicrosecond scale

open access: yesEPJ Web of Conferences, 2018
Kh16N15M3T1 and Kh13V2 reactor steels were investigated. The study was carried out using a light-gas gun with the deformation velocities ranging from 4·104 to 3·106 s-1 and shock-loading pulses in 0.05-1 μs duration range.
Mokrushin Sergey S.   +6 more
doaj   +1 more source

Effects of Cr and Si on the microstructure and solidification path of austenitic stainless steel

open access: yes工程科学学报, 2020
The lead-cooled fast reactor (LFR), which features advanced technical maturity and enhanced safety, is an important part of the fourth-generation nuclear power system of China.
Hao-yu YI   +4 more
doaj   +1 more source

DESIGN CRITERIA FOR STEEL IN NUCLEAR REACTORS [PDF]

open access: yes, 1961
S>Criteria for stress analysis and structural design with steel for the critical components of nuclear plants are presented. An effort was made to integrate the effects on the strength of steel of the coexisting phenomena, such as mechanical and thermal loads, stress cycling and fatigue, creep and creep rupture, irradiation, and loss of ductility ...
openaire   +2 more sources

MAGNETIC NONDESTRUCTIVE INSPECTION OF REACTOR STEEL CLADDED BLOCKS

open access: yesGJAETS - Global Journal of Advanced Engineering Technologies and Sciences, 2019
Degradation of nuclear pressure vessel steel material (15H2NMFA) was investigated by a novel magnetic nondestructive testing method, so called Magnetic Adaptive Testing (MAT), which is based on systematic measurement and evaluation of minor magnetic hysteresis loops.
Vértesy, Gábor   +3 more
openaire   +2 more sources

Research and Application of Steels for Reactor Pressure Vessel of Nuclear Power Station

open access: yesTeshugang, 2010
Developed status of steels for nuclear reactor pressure vessel at home and abroad is presented including re- querulent for analysis and properties, metallurgical process, heat treatment, and present situation of manufacture and application. The developed
doaj  

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