Zobrazeno 1 - 10
of 66
pro vyhledávání: '"H.E. Rosinger"'
The ordered face-centered cubic (fcc) zirconium-aluminum phase (Zr 3 Al, Ll 2 type) is being evaluated as a future CANada Deuterium Uranium (CANDU) reactor pressure-tube material on the hypothesis that ordering may lead toa reduction in rates of atom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ddc867f81ba119ca7eef9183fcd2a65
https://doi.org/10.1520/stp35585s
https://doi.org/10.1520/stp35585s
Publikováno v:
Journal of Sound and Vibration. 47:585-588
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::912c8d124f8b202a30884e5b2cd25ab6
https://doi.org/10.1016/0022-460x(76)90885-3
https://doi.org/10.1016/0022-460x(76)90885-3
Publikováno v:
Journal of Nuclear Materials. 82:286-297
Steady-state creep rates of as-received zircaloy-4 fuel cladding have been determined from 940 to 1073 K in the α-Zr range, from 1140 to 1190 K in the mixed (α + β) phase region and from 1273 to 1873 K in the β-Zr phase region. Strain rates of be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d02ccf0536cebcf7df595a2e8722d509
https://doi.org/10.1016/0022-3115(79)90011-4
https://doi.org/10.1016/0022-3115(79)90011-4
Autor:
H.E. Rosinger
Publikováno v:
Journal of Nuclear Materials. 66:193-196
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e427e5f0feb738bc18e9e3b4604ad2a7
https://doi.org/10.1016/0022-3115(77)90146-5
https://doi.org/10.1016/0022-3115(77)90146-5
Publikováno v:
Journal of Nuclear Materials. 90:256-267
Specimens of a Zr-8.6wt%Al hypoperitectoid alloy have been irradiated at 600 K in a thermal reactor environment and at temperatures in the range 541–758 K in a fast reactor environment. The irradiation growth, density changes and structural modific
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d3e3f048a41cd21326e2a8faf4d42829
https://doi.org/10.1016/0022-3115(80)90263-9
https://doi.org/10.1016/0022-3115(80)90263-9
Autor:
H.E. Rosinger
Publikováno v:
Journal of Nuclear Materials. 95:171-180
The influence of fast neutron irradiation (E > 1 MeV) at 600 K on the growth, mechanical properties and fracture toughness of Zr3Al-based alloys has been investigated for neutron fluences of up to 2.3 × 1025n/m2. The Zr3Al intermetallic grows under
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1d54afca9bbbcc61a1c18e37f5de7f49
https://doi.org/10.1016/0022-3115(80)90091-4
https://doi.org/10.1016/0022-3115(80)90091-4
Autor:
H.E. Rosinger, Derek O. Northwood
Publikováno v:
Journal of Nuclear Materials. 89:147-154
The dynamic elastic moduli of Zircaloy-4 containing 1000–7300 ppm oxygen (by weight) have been determined over the temperature range room temperature to 1000°. The addition of oxygen as surface oxide layer increased both the elastic modulus and sh
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6257bf0420607d52eab60207392673b6
https://doi.org/10.1016/0022-3115(80)90019-7
https://doi.org/10.1016/0022-3115(80)90019-7
Autor:
J. Ferner, H.E. Rosinger
Publikováno v:
Journal of Nuclear Materials. 132:167-172
A failure model for Zircaloy-4 fuel cladding was previously developed and used to predict the effect of circumferential temperature variation (Δ T ) on fuel cladding failure in inert atmospheres. This work was undertaken to generate experimental dat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::13350c8bde16ace5ac2d207d5ac4aa6b
https://doi.org/10.1016/0022-3115(85)90411-8
https://doi.org/10.1016/0022-3115(85)90411-8
Autor:
B.J.S. Wilkins, H.E. Rosinger
Publikováno v:
Journal of Nuclear Materials. 89:347-353
The effect of fast neutron irradiation at 600 K on the tensile properties and fracture toughness of a Zr3Al-based alloy (Zr-8.6wt%Al) has been studied for fluences up to 2.4 × 1025 n/m2 (E > 1 MeV). For neutron fluences 1025 n/m2 are explained in te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::988e196c22363dfa269f45750d008a82
https://doi.org/10.1016/0022-3115(80)90066-5
https://doi.org/10.1016/0022-3115(80)90066-5
Autor:
Derek O. Northwood, H.E. Rosinger
Publikováno v:
Journal of Nuclear Materials. 79:170-179
A knowledge of the elastic properties of zirconium alloys is required in the mathematical modelling of cladding and pressure tubing performance. Until recently, little of this type of data was available, particularly at elevated temperatures. The dyn
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6df4f250a191077bb964fd03c31ea6d
https://doi.org/10.1016/0022-3115(79)90444-6
https://doi.org/10.1016/0022-3115(79)90444-6