Zobrazeno 1 - 10
of 15
pro vyhledávání: '"SK Iskander"'
Publikováno v:
Materials Science and Engineering: A. 327:76-79
The compositions of the matrices of welds in a pressure vessel steel have been determined by atom probe tomography after a series of stress relief treatments. The weld had a bulk composition of Fe–0.29 at.% Cu–1.69 at.% Mn–0.54 at.% Ni–0.69 a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::14fe4bfa8c7135e0d82bdd9d49bf65e8
https://doi.org/10.1016/s0921-5093(01)01879-2
https://doi.org/10.1016/s0921-5093(01)01879-2
Publikováno v:
Nuclear Engineering and Design. 134:227-243
In light-water-cooled nuclear power plants, a steel reactor pressure vessel (RPV) forms the primary containment boundary for the nuclear fuel assembly. Since a failure of the RPV carries the potential of major contamination release and severe acciden
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d5724fa0d7b3f510d9425b742b6b9cd7
https://doi.org/10.1016/0029-5493(92)90141-h
https://doi.org/10.1016/0029-5493(92)90141-h
The thermal annealing response of several materials as indicated by Charpy transition temperature (TT) and upper-shelf energy (USE), crack initiation toughness, K{sub Jc}, predictive models, and automated-ball indentation (ABI) testing are compared.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5720e6bb5f712d5bfbdf4a7131fc6598
https://doi.org/10.1520/stp13878s
https://doi.org/10.1520/stp13878s
The objective of this investigation is an estimation of the crack-arrest toughness, particularly of irradiated materials, from voltage versus time output of an instrumented setup during a test on a Charpy V-notch (CVN) specimen. This voltage versus t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::93d859b58e193030a64fb4823786f929
https://doi.org/10.1520/stp13865s
https://doi.org/10.1520/stp13865s
Flaw behavior trends associated with pressurized thermal shock (PTS) loading of pressurized water reactor (PWR) pressure vessels have been under investigation at Oak Ridge National Laboratory (ORNL) for approximately twelve years. During that time, e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a085e320c4ed6edc565bdd1932280b0f
https://doi.org/10.1520/stp33104s
https://doi.org/10.1520/stp33104s