Zobrazeno 1 - 10
of 36
pro vyhledávání: '"B. Kammenzind"'
Akademický článek
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Publikováno v:
Journal of Nuclear Materials. 532:152055
A new interatomic embedded atom method (EAM) potential, called BMD19, has been developed for simulations of hexagonal zirconium with dissolved hydrogen. The parameters are fitted to data from density functional calculations and calibrated using the e
Akademický článek
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Autor:
Anthony Stern, Jean-Christophe Brachet, Valérie Maillot, Didier Hamon, Françoise Barcelo, Sylvie Poissonnet, André Pineau, Jean-Paul Mardon, Anne Lesbros, M. Limback, B. Kammenzind, S. W. Dean
Publikováno v:
Journal of ASTM International (JAI)
Journal of ASTM International (JAI), ASTM, 2008, 5, pp.71-90. ⟨10.1520/JAI101119⟩
Journal of ASTM International (JAI), 2008, 5, pp.71-90. ⟨10.1520/JAI101119⟩
Journal of ASTM International (JAI), ASTM, 2008, 5, pp.71-90. ⟨10.1520/JAI101119⟩
Journal of ASTM International (JAI), 2008, 5, pp.71-90. ⟨10.1520/JAI101119⟩
International audience; It is now well acknowledged that, after a prototypical loss of coolant accident (LOCA) transient, the resultant mechanical properties of fuel cladding tubes depend strongly on the oxygen content of the residual prior-β layer,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fed2a12cd9ab6b63a11c2e7770ae6f0a
https://hal-mines-paristech.archives-ouvertes.fr/hal-00488994
https://hal-mines-paristech.archives-ouvertes.fr/hal-00488994
Akademický článek
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Autor:
Jeong-Yong Park, Byung-Kwon Choi, Seung Jo Yoo, Yong Hwan Jeong, M. Limback, B. Kammenzind, S. W. Dean
Publikováno v:
Journal of ASTM International. 5:101129
The corrosion behavior of HANA alloys has been investigated at 360°C in a pure water autoclave as well as in a pressurized water reactor (PWR)-simulating loop. The grain morphology and the incorporated precipitates of the oxide were characterized to
Autor:
Robert S. Daum, Saurin Majumdar, Michael C. Billone, Magnus Limback, B. Kammenzind, S. W. Dean
Publikováno v:
Journal of ASTM International. 5:101209
Sufficient mechanical ductility of high-burnup Zircaloy-4 fuel cladding is important to prevent large-opening ruptures and significant fuel dispersal during postulated in-reactor and spent-fuel processing accidents. The effect of irradiation, oxidati
Publikováno v:
Journal of ASTM International. 5:101110
The phenomenon of stress reorientation of hydrides in fuel cladding tubes was studied with the help of a test technique named as the “cladding tube deformation test” (CTDT). Unirradiated Zircaloy-2 (Zry-2) cladding tube specimens charged with 250
Autor:
V. N. Shishov, M. M. Peregud, A. V. Nikulina, V. F. Kon’kov, V. V. Novikov, V. A. Markelov, T. N. Khokhunova, G. P. Kobylyansky, A. E. Novoselov, Z. E. Ostrovsky, A. V. Obukhov, M. Limback, B. Kammenzind, S. W. Dean
Publikováno v:
Journal of ASTM International. 5:101127
In the search for more optimal core materials for a water cooled reactor at extended burnup, much attention is paid to alloys of the Zr-Nb and Zr-Nb-Fe-Sn systems. E110 and E635 alloys are two such. In the current VVER fuel cycle, the E110 alloy is u
Publikováno v:
Journal of ASTM International. 5:101121
The microstructure of oxide films formed on Zircaloy-4 and Alloy No. 3, which has a composition similar to ZIRLO™, was investigated by high resolution transmission and scanning electron microscopy, and by scanning probe microscopy after corrosion t