Zobrazeno 1 - 10
of 162
pro vyhledávání: '"V. Fidleris"'
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
The Hanford N Reactor contains 1004 cold-worked Zircaloy-2 pressure tubes made by four different fabrication routes. They operate at 395 to 560/sup 0/F (475 to 566 K) with a hoop stress of 8400 psi (58 MPa) and a peak neutron flux of 2.2 x 10/sup 13/
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d2688e5c3f24e0bf3070b94a083cf94
https://doi.org/10.1520/stp35580s
https://doi.org/10.1520/stp35580s
The dislocation microstructures of annealed Zircaloy-2, cold-worked Zr-2.5 wt% Nb and extruded Excel (Zr-3.5 wt% Sn-0.8 wt% Nb-0.8 wt% Mo) neutron irradiated in EBR-II at 670 to 690 K to fluences of 1.7 to 6.3 x 10/sup 25/ n/m/sup 2/ (E>1 MeV) and al
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::45f10fd8d033dfeae7e4d8889b333907
https://doi.org/10.1520/stp34348s
https://doi.org/10.1520/stp34348s
Autor:
V Fidleris
Primary in-reactor creep of Zircaloy-2 exhibits approximately linear plots of log(creep strain, e) against log(test time, t) that fit relations of the type e = βt m . For longitudinal specimens of cold-worked Zircaloy-2 atabout 570 K, neutron flux o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c74516611bc588603d9b1a6a90fb42c1
https://doi.org/10.1520/stp36679s
https://doi.org/10.1520/stp36679s
Pressure tubes for CANada Deuterium Uranium Pressurized Heavy Water reactors are made from Zr-2.5Nb by extruding preheated hollow billets into tubes that are cold-worked 30 percent to size. The fabrication process produces fine elongated α-grains wi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::32f4c1dfc8197890cccfd0d6a183bc4e
https://doi.org/10.1520/stp37055s
https://doi.org/10.1520/stp37055s
Irradiation growth behavior of Zircaloy-2 and -4 was studied on specimens irradiated in an experimental breeder reactor. Measurements on Zircaloy-2 slab materials provided evidence that growth was a constant volume process up to 680 K. The growth str
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b93b86addf21309d2fb4d77b04ef6bc0
https://doi.org/10.1520/stp37056s
https://doi.org/10.1520/stp37056s
Autor:
V. Fidleris, B. Cox
The linear growth of relatively thick (>300 nm) interference-colored oxide films on zirconium alloy specimens exposed in the Advanced Test Reactor (ATR) coolant at ≤55°C was unexpected. Initial ideas were that this was a photoconduction effect. Ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::755a69350e53a8bf74d6bbfc25d2ba31
https://doi.org/10.1520/stp18869s
https://doi.org/10.1520/stp18869s