Results 161 to 170 of about 1,137 (200)
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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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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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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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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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Irradiation-Embrittlement of Reactor Pressure Vessel Steel
18th International Conference on Nuclear Engineering: Volume 5, 2010Irradiated for 4 cycles inside the reactor, the irradiation surveillance capsule (ISC) was withdrawn and transported to Nuclear Power Institute of China (NPIC) for dismantling in the hot cell. This paper presented tensile tests and Charpy-V impact tests on non-irradiated and irradiated specimens. Tensile tests were performed at room temperature and 300
Guoyun Li +4 more
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Evaluation of Irradiation Embrittlement of the Chinese RPV Steels
Volume 6A: Materials and Fabrication, 2019Abstract Reactor pressure vessel (RPV) is considered to be irreplaceable, which is the most limiting factor for the lifetime of a nuclear power plant. This paper aims to introduce our project for the evaluation of the irradiation embrittlement for the Chinese RPV forging.
Yupeng Cao +6 more
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Irradiation embrittlement characterization of the EUROFER 97 material
Journal of Nuclear Materials, 2011The paper summarizes original results of irradiation embrittlement study of EUROFER 97 material that has been proposed as one candidate of structural materials for future fusion energy systems and GEN IV. Test specimens were manufactured from base metal as well as from weld metal and tested in initial unirradiated condition and also after neutron ...
M. Kytka, M. Brumovsky, M. Falcnik
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A phenomenological theory of the irradiation embrittlement of iron and steel
Journal of Nuclear Materials, 1969Abstract The shift of the ductile-brittle transition temperature with neutron irradiation is structure sensitive. In this study, the effect of micro-structure on the transition temperature of iron and steel, before and after irradiation, is analysed and discussed.
N. Igata, R.R. Hasiguti
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Solutions to the Problems of High-Temperature Irradiation Embrittlement
1967The effects of irradiation on high-temperature mechanical properties of structural materials is described using Type 304 stainless steel as an example. The general effect is one in which the grain-boundary fracture process, but not the deformation process, is affected.
W. R. Martin, J. R. Weir
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The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature
1996Assessments of the hardening and embrittlement of pressure vessel steels and welds as a function of neutron dose use trend curves derived from surveillance programmes and accelerated irradiation data. A temperature dependent factor is incorporated for assessing vessel locations operating at different temperatures.
RB Jones, TJ Williams
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