Results 11 to 20 of about 3,105,065 (231)
Validation of RT(T0) for German reactor pressure vessel steels
Journal of Pressure Vessel Technology, 2022 Art. 031405, 6 S.For the introduction of the new reference temperature RTT0 of the ASME Code Cases N-629 and N-631 into the German Standard KTA 3201.2, the applicability of RTT0 was validated by the reevaluation of the existing fracture toughness ...
Keim, E., Siegele, D., Nagel, G.
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Analysis of Surface Roughness Influence in Non-Destructive Magnetic Measurements Applied to Reactor Pressure Vessel Steels [PDF]
Applied Sciences, 2020 The influence of surface roughness on magnetic measurements of Reactor Pressure Vessel Steels was investigated by applying two types of magnetic, non-destructive measurement on nuclear reactor pressure vessel steel samples: magnetic adaptive testing (MAT)
Gábor Vértesy +5 more
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Research Progress of Steels for Nuclear Reactor Pressure Vessels. [PDF]
Materials (Basel), 2022 The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel.
Zhou L +6 more
europepmc +3 more sources
Use of master curve technology for assessing shallow flaws in a reactor pressure vessel material
, 2022 Art. 031407, 11 S.In the NESC-IV project, an experimental/analytical program was performed to develop validated analysis methods for transferring fracture toughness data to shallow flaws in reactor pressure vessels subject to biaxial loading in the lower-
Wintle, J. +6 more
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UK Rules For Unfired Pressure Vessels [PDF]
, 2008 The present code PD 5500, formerly BS 5500 [1] evolved partly from the well-known BS 1500 [2] in the 1950's and BS 1515 [3] first published in 1965; the latter permitted higher level allowable stresses and more advanced rules. In 1969, following a report
Nash, David H.
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Metals, 2022 Understanding the mechanical behaviour of reactor pressure vessel (RPV) steels at high fluences has become an important topic in regard to Long-Term Operations (LTO) of existing nuclear power plants (NPP).
Mathilde Laot +5 more
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, 2022 S.101-111In order to avoid extensive and expensive testing of the J(R) crack resistance behavior of reactor pressure vessel steels, different correlations between the upper shelf energy obtained from Charpy impact tests and the crack resistance curve ...
Siegele, D. +3 more
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Machine learning predictions of irradiation embrittlement in reactor pressure vessel steels
npj Computational Materials, 2022 Irradiation increases the yield stress and embrittles light water reactor (LWR) pressure vessel steels. In this study, we demonstrate some of the potential benefits and risks of using machine learning models to predict irradiation hardening extrapolated ...
Yu-chen Liu +20 more
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Nuclear Materials and Energy, 2023 Neutron embrittlement of reactor pressure vessel (RPV) steels potentially limits the safe operational time of nuclear reactors. In tested RPV steel samples microcracks are known to originate from cleaved precipitates, inclusions or grain boundaries ...
Paul Chekhonin +3 more
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Conducting local cutout from the surface of the VVER-1000 reactor vessel
Trudy Odesskogo Politehničeskogo Universiteta, 2019 Integrity of the reactor pressure vessel is a critical element in demonstrating the capability of nuclear power plant for operation to at least 80 years.
Олексій Геннадійович Руденко +3 more
doaj +5 more sources