Results 161 to 170 of about 1,250 (204)
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Irradiation embrittlement of ferritic stainless steels
Metal Science, 1984AbstractThe characteristics of the irradiation embrittlement of some ferritic stainless steels were examined by tensile tests. Steels selected in this investigation were classified into three groups: X phase, precipitation hardened Fe-13Cr steels; tempered martensitic Fe-12Cr steels; and low alloy steels.
K. Suganuma, H. Kayano
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Irradiation embrittlement mitigation
1993Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered ...
Pelli, Reijo +4 more
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Assessment of irradiation embrittlement of the Eurofer97 steel after 590MeV proton irradiation
Journal of Nuclear Materials, 2009The irradiation hardening of the Eurofer97 steel following 590 MeV proton irradiations was determined at three different irradiation temperatures, 50 °C, 250 °C and 350 °C, and various doses up to about 1.3 displacement per atom. The dose and temperature dependence of the irradiation hardening was characterized by a linear relationship between the ...
Spätig, P. +4 more
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Embrittlement of irradiated ferritic/martensitic steels in the absence of irradiation hardening
Journal of Nuclear Materials, 2008Irradiation damage caused by neutron irradiation below 425–450 C of 9–12% Cr ferritic/martensitic steels produces microstructural defects that cause an increase in yield stress. This irradiation hardening causes embrittlement observed in a Charpy impact test as an increase in the ductile–brittle transition temperature.
R.L. Klueh, K. Shiba, M.A. Sokolov
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Irradiation embrittlement of neutron-irradiated low activation ferritic steels
Journal of Nuclear Materials, 1988Abstract Effects of neutron irradiation and additions of small amounts of alloying elements on the ductile-brittle transition temperature (DBTT) of three different groups of ferritic steels were investigated by means of the Charpy impact test in order to gain an insight into the development of low-activation ferritic steels suitable for the nuclear ...
H. Kayano +5 more
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Hydrogen Embrittlement Characteristics in Irradiated Stainless Steel
Volume 12: Mechanics of Solids, Structures, and Fluids, 2020Abstract Hydrogen is produced in nuclear reactors as a by-product of the corrosion reaction between the pressure vessel and the cooling water, where hydrogen produced may enter the metal in atomic form. During operation a reactor vessel is exposed to avalanche of neutron irradiation fluxes, in addition to corrosion from cooling water.
Tarek Hatem, Sarah Khalil
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Descriptive characteristics of different types of test for irradiation embrittlement
Nuclear Engineering and Design, 1995An extensive evaluation of three different materials in the as-received and irradiated condition has been carried out in Finland. The mechanical properties measured at different temperatures include tensile data, Charpy-V notch and instrumented precracked Charpy data and elastic-plastic fracture toughness.
Wallin, Kim +4 more
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Irradiation Embrittlement in Some Austenitic Superalloys
1982The nature of the irradiation embrittlement phenomenon in selected austenitic superalloys was evaluated in tubular specimens compression tested at elevated temperatures. Materials included the commercial alloys Inconel 706 and Nimonic PE-16 and two experimental alloys. All are precipitation hardenable and were irradiated from 2.8 to 7.1 × 1022 n/cm2 (E&
S Vaidyanathan, T Lauritzen, WL Bell
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Neutron irradiation embrittlement of molybdenum single crystals
Journal of Nuclear Materials, 1986Tensile tests at room temperature to 600°C were performed on molybdenum single crystals which had been neutron irradiated to a fluence of 6.6 × 1023n/m2 (E > 1 MeV). The single crystals were prepared by means of secondary recrystallization and had axial orientations that were near to the 〈011〉-direction. The increase in yield strength and the degree
Yutaka Hiraoka +4 more
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Embrittlement behavior of neutron irradiated RAFM steels
Journal of Nuclear Materials, 2007Abstract The effects of neutron irradiation on the embrittlement behavior of reduced activation ferritic/martensitic (RAFM) steel EUROFER97 for different heat treatment conditions have been investigated. The irradiation to 16.3 dpa at different irradiation temperatures (250–450 °C) was carried out in the Petten High Flux Reactor in the framework of ...
Gaganidze, E. +3 more
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