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Author : L. D. Perrigo
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 (91 download)
Download or read book Oxide Tenacity on Alloys Exposed to Reactor Coolants written by L. D. Perrigo and published by . This book was released on 1963 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 476 pages
Book Rating : 4.:/5 (3 download)
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1964 with total page 476 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 288 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reactor Materials written by and published by . This book was released on 1965 with total page 288 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 664 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Applications written by and published by . This book was released on 1965 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 2300 pages
Book Rating : 4.E/5 ( download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1964 with total page 2300 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : American Nuclear Society
Publisher :
ISBN 13 :
Total Pages : 614 pages
Book Rating : 4.3/5 (91 download)
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1964 with total page 614 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : International Atomic Energy Agency
Publisher :
ISBN 13 :
Total Pages : 838 pages
Book Rating : 4.:/5 (334 download)
Download or read book List of References on Nuclear Energy written by International Atomic Energy Agency and published by . This book was released on 1964-07 with total page 838 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 (91 download)
Download or read book Hanford Formal Research and Development Reports ... written by and published by . This book was released on 1964 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Institute of Metals
Publisher :
ISBN 13 :
Total Pages : 1144 pages
Book Rating : 4.3/5 (91 download)
Download or read book Journal of the Institute of Metals written by Institute of Metals and published by . This book was released on 1964 with total page 1144 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Institute of Metals
Publisher :
ISBN 13 :
Total Pages : 1094 pages
Book Rating : 4.F/5 ( download)
Download or read book Metallurgical Abstracts written by Institute of Metals and published by . This book was released on 1964 with total page 1094 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 35 pages
Book Rating : 4.:/5 (727 download)
Download or read book Oxidation of Zirconium Alloys in 2.5 KPa Water Vapor for Tritium Readiness written by and published by . This book was released on 2007 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt: A more reactive liner material is needed for use as liner and cruciform material in tritium producing burnable absorber rods (TPBAR) in commercial light water nuclear reactors (CLWR). The function of these components is to convert any water that is released from the Li-6 enriched lithium aluminate breeder material to oxide and hydrogen that can be gettered, thus minimizing the permeation of tritium into the reactor coolant. Fourteen zirconium alloys were exposed to 2.5 kPa water vapor in a helium stream at 300 C over a period of up to 35 days. Experimental alloys with aluminum, yttrium, vanadium, titanium, and scandium, some of which also included ternaries with nickel, were included along with a high nitrogen impurity alloy and the commercial alloy Zircaloy-2. They displayed a reactivity range of almost 500, with Zircaloy-2 being the least reactive.
Author : U.S. Atomic Energy Commission. Division of Technical Information
Publisher :
ISBN 13 :
Total Pages : 866 pages
Book Rating : 4.F/5 ( download)
Download or read book Reports Received by Division of Technical Information Extension written by U.S. Atomic Energy Commission. Division of Technical Information and published by . This book was released on with total page 866 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Jamie Kunkle
Publisher :
ISBN 13 :
Total Pages : 146 pages
Book Rating : 4.:/5 (613 download)
Download or read book Structure of Oxide Layers Formed on Candidate Steel Alloys Exposed to Flowing Lead-bismuth Eutectic for Generation IV Reactor Applications written by Jamie Kunkle and published by . This book was released on 2009 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic-martensitic steels of interest for use in Generation IV lead cooled fast reactors were corroded in a flowing lead-bismuth eutectic environment and the microstructures of the oxide layers they formed were characterized using microbeam synchrotron radiation. Five samples were studied, four of which (HT-9, HT-9 Annealed, T91, and a model alloy) were corroded at 500°C for 666 hours and one of which (HT-9) was corroded at 550°C for 3000 hours in flowing lead bismuth eutectic environments. Studies performed on oxide layers using microbeam synchrotron radiation yielded a detailed view of fluorescence and diffraction data from each of the oxide layers and sublayers formed. Each alloy exhibited a duplex oxide structure consisting of an inner and outer oxide layer. The interface of these two layers corresponded to the original pre-corrosion metal surface. In general, the oxide layers appeared to have been formed in a manner similar to those formed in other gaseous and liquid environments i.e. via the simultaneous ingress of oxygen (O2- ) and egress of iron (Fe2+) across the inner oxide - outer oxide interface. The outer oxide layers observed were formed entirely of Fe3O4 magnetite, contained contaminates (Pb, Bi) from the coolant, and showed evidence of liquid metal dissolution. Inner oxide layers were formed primarily from Fe3O4, but also contained retained ferrite from the bulk metal, carbides, and chromium oxides. Chromium oxides, specifically Cr2O3, are known to act as barriers against the diffusion of oxygen and iron in these materials, slowing oxidation in these materials. The retained bcc iron, or ferrite, in the inner oxide combined with preferential oxidation along lath boundaries suggest that the oxide front advancement proceeded into the metal via preferential oxidation along lath boundaries, followed by selective oxidation of the laths.
Author : United States. Delegation to the International Conference on the Peaceful Uses of Atomic Energy
Publisher :
ISBN 13 :
Total Pages : 148 pages
Book Rating : 4.3/5 (91 download)
Download or read book Atoms for Peace Conference, 1964 written by United States. Delegation to the International Conference on the Peaceful Uses of Atomic Energy and published by . This book was released on 1965 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Atomic Energy Commission
Publisher :
ISBN 13 :
Total Pages : 148 pages
Book Rating : 4.:/5 (319 download)
Download or read book Atoms for Peace Conference, 1964; Third United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, Switzerland, August 31- Sept. 9, 1964, a Report by the United States Delegation written by U.S. Atomic Energy Commission and published by . This book was released on 1965 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : B. Cox
Publisher :
ISBN 13 :
Total Pages : 21 pages
Book Rating : 4.:/5 (125 download)
Download or read book Enhanced Low-Temperature Oxidation of Zirconium Alloys Under Irradiation written by B. Cox and published by . This book was released on 1989 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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. Experiments to study photoconduction in thin anodic zirconium oxide (ZrO2) films in the laboratory were initiated to provide background data. It was found that, in the laboratory, provided a high electric field was maintained across the oxide during ultraviolet (UV) irradiation, enhanced growth of oxide occurred in the irradiated area. Similarly enhanced growth could be obtained on thin thermally formed oxide films that were immersed in an electrolyte with a high electric field superimposed. This enhanced growth was found to be caused by the development of porosity in the barrier oxide layer by an enhanced local dissolution and reprecipitation process during UV irradiation. Similar porosity was observed in the oxide films on the ATR specimens. Since it is not thought that a high electric field could have been present in this instance, localized dissolution of fast-neutron primary recoil tracks may be the operative mechanism. In all instances, the specimens attempt to maintain the normal barrier-layer oxide thickness, which causes the additional oxide growth. Similar mechanisms may have operated during the formation of thick loosely adherent, porous oxides in homogeneous reactor solutions under irradiation, and may be the cause of enhanced oxidation of zirconium alloys in high-temperature water-cooled reactors in some water chemistries.
Author : A. B. Johnson
Publisher :
ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.:/5 (125 download)
Download or read book Effects of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys written by A. B. Johnson and published by . This book was released on 1969 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of in-reactor corrosion tests was conducted in the G-7 loop of the Engineering Test Reactor (ETR) in pH 10 NH4OH at 270 to 280 C. Six zirconium alloys were exposed in as-etched and prefilmed (400 C steam) surface conditions. The six alloys were Zircaloy-2, Zircaloy-4, Zr-3Nb-1Sn, Zr-2.5Nb, Zr-1.2Cu-0.28Fe, and Zr-1.2Cr-0.08Fe. Exposures were 25, 37, 77, and 174 days in high-flux, low-flux, out-of-flux, and out-of-reactor environments. Results from the 174-day exposure are emphasized, but corrosion and hydriding data from the complete test series are compared.
