Results 11 to 20 of about 1,250 (204)

To the issue of accuracy of determination of irradiation embrittlement coefficient [PDF]

open access: yesЯдерна фізика та енергетика, 2020
The paper presents the statistical analysis of experimental results of radiation-induced critical brittle temperature ΔTF shifts and reference temperatures ΔT0 obtained respectively from the impact bend and fracture toughness tests of the reactor vessel ...
L. I. Chyrko   +5 more
doaj   +2 more sources

Hydrogen embrittlement in irradiated steels [PDF]

open access: yesNuclear Engineering and Design, 1966
Abstract Hydrogen charging conditions that completely embrittle an ultra-high strength steel have a negligible effect on 212-B pressure vessel steel in tensile and delayed failure tests, Much higher hydrogen charges reduce the notch tensile strength.
A.D. Rossin, T.H. Blewitt, A.R. Troiano
openaire   +3 more sources

Control of Irradiation Embrittlement in Molybdenum [PDF]

open access: yesNature, 1961
IRON, steel, and other body-centred cubic metals show an increase in ductile-brittle transition temperature as a result of neutron irradiation. In an attempt to elucidate the mechanism of this embrittlement for EN2 steel, Hull and Mogford1 studied the effect of neutron irradiation on the parameters σi and k y in the Petch relation:
D. N. SETHNA   +3 more
openaire   +1 more source

Nondestructive Investigation of Neutron Irradiation Generated Structural Changes of Reactor Steel Material by Magnetic Hysteresis Method

open access: yesMetals, 2020
The neutron irradiation embrittlement of four different types of nuclear pressure vessel materials (three base metals and one weld material) were investigated by a magnetic nondestructive testing method, magnetic adaptive testing (MAT).
Gábor Vértesy   +5 more
doaj   +1 more source

Irradiation Embrittlement of WWER RPV Steels Irradiated at High Fluences [PDF]

open access: yesJournal of Nuclear Technology in Applied Science, 2020
A statistical analysis of data obtained during impact testing of surveillance specimen of 15 WWER-440 RPVs operating in Russia, Ukraine, Armenia, Hungary, the Czech Republic and Slovakia was performed. The raw data used were selected from the IAEA International Database. As a result of the analysis, the influence of P and Cu to Tk increase was observed
Alexander Kryukov   +2 more
openaire   +1 more source

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

open access: yesNuclear 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   +8 more
doaj   +1 more source

Development of innovative materials and thermal treatments for DEMO water cooled blanket

open access: yesNuclear Materials and Energy, 2019
One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled lanket”. This option implies an irradiation temperature for the blanket material in the range of 280–350 °C.
L. Pilloni   +5 more
doaj   +1 more source

Limited field radiation therapy results in decreased bone fracture toughness in a murine model. [PDF]

open access: yesPLoS ONE, 2018
Fragility fractures are a well-known complication following oncologic radiotherapy, and it is suspected that radiation-induced embrittlement of bone within the treatment field may contribute to fracture risk.
Christopher M Bartlow   +3 more
doaj   +1 more source

Master curve testing of RPV steels using mini-C(T) specimens – Irradiation effects and censoring statistics

open access: yesNuclear Materials and Energy, 2023
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase in the reference temperature (T0) of the RPV steel and reduces the operating lifetime of nuclear reactors. Fracture mechanics testing of RPV steels before
A. Das   +4 more
doaj   +1 more source

On the Limitations of Positron Annihilation Spectroscopy in the Investigation of Ion-Implanted FeCr Samples

open access: yesMetals, 2021
New materials for advanced fission/fusion nuclear facilities must inevitably demonstrate resistance to radiation embrittlement. Thermal and radiation ageing accompanied by stress corrosion cracking are dominant effects that limit the operational ...
Vladimir Slugen   +5 more
doaj   +1 more source

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