Zobrazeno 1 - 10
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pro vyhledávání: '"D. Khatamian"'
Autor:
D. Khatamian
Publikováno v:
Journal of Alloys and Compounds. 580:S58-S62
Pressure tubes of cold-worked Zr–2.5Nb material are used in the CANDU (CANada Deuterium Uranium is a registered trademark of Atomic Energy of Canada Ltd.) reactors to contain the fuel bundles and the heavy water coolant. The pressure tube microstru
Autor:
D. Khatamian
Publikováno v:
The Journal of Supercritical Fluids. 78:132-142
To increase the thermodynamic efficiency above 40% in nuclear power plants, the use of supercritical water as the heat transport fluid has been suggested. Zircaloy-2, -4, Zr–Cr–Fe, Zr–1Nb and Zr–2.5Nb were tested as prospective fuel cladding
Autor:
D. Khatamian
Publikováno v:
Journal of Alloys and Compounds. 509:S797-S800
Pressure tubes of cold-worked Zr–2.5Nb (Zr–2.5 wt% Nb) material are used in the core of CANDU ® 1 reactors to contain the fuel bundles and the heavy water (D 2 O) heat transport fluid. Deuterium diffusion in unirradiated Zr–2.5Nb pressure tube
Autor:
D. Khatamian
Publikováno v:
Journal of Nuclear Materials. 405:171-176
One of the concerns of the nuclear industry is the deleterious effect of hydrogen on the structural integrity of the reactor core components due to delayed hydride cracking (DHC). The DHC process occurs when hydrogen concentration exceeds the termina
Autor:
D. Khatamian
Publikováno v:
Defect and Diffusion Forum. :631-640
Transport of hydrogen through oxide layers formed on zirconium alloys has been the focus of studies associated with hydrogen ingress into nuclear reactor core components. The studies have shown that microstructure and microchemistry of the underlying
Autor:
D. Khatamian, John H. Root
Publikováno v:
Journal of Nuclear Materials. 372:106-113
Due to their low absorption cross-section for neutrons, Zr alloys are used for reactor core components. The terminal solid solubility (TSS) for hydrogen in these alloys is very low – in Zr–2.5 wt% Nb, used to fabricate pressure tubes for CANDU (C
Autor:
D. Khatamian
Publikováno v:
Journal of Alloys and Compounds. :297-302
This study was initiated to determine the role of hydrides on the oxidation and D-pickup rates of Zr–2.5Nb pressure tubes used in CANDU ® 1 reactors. Coupons of Zr–2.5Nb pressure tube material were charged to H concentrations ranging from 5 to 8
Autor:
D. Khatamian
Publikováno v:
Journal of Alloys and Compounds. :22-26
The zirconium alloy Zr–2.5Nb (Zr–2.5 wt.% Nb) is used to fabricate pressure tubes for CANDU ® 1 nuclear reactors. The microstructure of the as-extruded tubes consists of elongated h.c.p. α-Zr grains surrounded by a network of b.c.c. β-Zr conta
Publikováno v:
Acta Materialia. 51:2041-2053
When the concentration of hydrogen exceeds the solubility limit in a metal matrix, metal hydrides may appear as precipitates that degrade the performance of the material. Neutron diffraction was combined with microscopy to study the [delta] to [gamma
Publikováno v:
Materials at High Temperatures. 20:593-600
The microstructures of oxides grown on the inside surface (water-side) of Zr–2.5Nb pressure tubes removed from CANDU® reactors were characterised by TEM and correlated with deuterium ingress. Oxide cross-sections consisted of two structurally dist