Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume) 1993
DOI: 10.1520/stp24780s
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Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program

Abstract: Test blocks of a manganese-nickel-molybdenum (Mn-Ni-Mo) low-alloy steel, machined from a nozzle cut-out of a 230-mm-thick forging shell, were provided by France in 1978 to be investigated in the second phase of an IAEA-coordinated research program on the behavior of advanced pressure vessel steels under neutron irradiation. The results obtained by different laboratories exhibit a great deal of scatter in Charpy-V transition temperatures, both in the initial condition and after neutron irradiatio… Show more

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Cited by 11 publications
(7 citation statements)
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“…The fit parameters are listed in Table 1. The overall quality of the fit is satisfactory whereas the extracted value of the transition temperature shift after irradiation, dT 0 % 103 K, is close to the value reported by the authors, dT DBT = 111 K [8]. By rescaling the energy and temperature (Eq.…”
Section: Comparison With Experimentssupporting
confidence: 83%
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“…The fit parameters are listed in Table 1. The overall quality of the fit is satisfactory whereas the extracted value of the transition temperature shift after irradiation, dT 0 % 103 K, is close to the value reported by the authors, dT DBT = 111 K [8]. By rescaling the energy and temperature (Eq.…”
Section: Comparison With Experimentssupporting
confidence: 83%
“…Fig. 1a displays data of Charpy V-notched specimens (referred hereafter to as CVN) for steel 16MND5 (close to grade ASME SA508C13) before and after irradiation [8], together with the best fits of Eq. (4) to the data.…”
Section: Comparison With Experimentsmentioning
confidence: 99%
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