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Kain, Vivekanand; Adhe, K.N.; Singh, P.R.; Sharma, B.P.
Cladding corrosion, embrittlement and pellet clad interaction: proceedings of theme meeting2005
Cladding corrosion, embrittlement and pellet clad interaction: proceedings of theme meeting2005
AbstractAbstract
[en] The oxidation behaviour of zirconium-1Nb, zirconium-2.5Nb and zircaloy-2 has been studied in 400deg C steam for 72 hours at 20 MPa with proper control of oxygen as per the procedure described in G 2M of ASTM. The oxide coatings were observed to be uniform and lustrous black. In a separate test, the Zr - 1 Nb samples were exposed in an autoclave in the same conditions without the control of oxygen and the oxygen content was high in this test. These tests showed about 5 fold increase in oxidation rate. In separate standard tests as per ASTM G 2M, it was shown that pressure (up to 20 MPa) does not play any significant role while etching (pickling) does affect the oxidation rates of Zr-1Nb material. (author)
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Source
Kale, G.B. (ed.) (Materials Science Div., Bhabha Atomic Research Centre, Mumbai (India)); Viswanadham, C.S. (ed.) (Laser Processing and Advanced Welding Section, Bhabha Atomic Research Centre, Mumbai (India)); Sah, D.N. (ed.) (Post Irradiation Examination Div., Bhabha Atomic Research Centre, Mumbai (India)); Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India); 179 p; Oct 2005; p. 46-54; HBINF-2005: 2. high burnup issues in nuclear fuels; Mumbai (India); 17 Oct 2005; 18 refs., 6 figs., 4 tabs
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Book
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Conference
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ALLOYS, ALLOY-ZR98SN-2, CHEMICAL REACTIONS, CHROMIUM ADDITIONS, CHROMIUM ALLOYS, CORROSION RESISTANT ALLOYS, DEPOSITION, ELEMENTS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRON ADDITIONS, IRON ALLOYS, MATERIALS, METALS, NICKEL ADDITIONS, NICKEL ALLOYS, REACTORS, REFRACTORY METALS, SURFACE COATING, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENTS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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