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Postirradiation Metallurgical Techniques to Estimate LOFT Peak Cladding Temperatures
A comprehensive review is presented of Zircaloy microstructure and oxidation characteristics. This information will be used to estimate LOFT peak cladding temperatures by metallographic analysis. Cladding temperatures expected for the LOFT L2-3 and L2-4 tests will be between 1050 and 1400 exp 0 K and their estimations present unique problems in using current metallographic data and techniques. (ERA citation 04:005879)
Postirradiation Metallurgical Techniques to Estimate LOFT Peak Cladding Temperatures
A comprehensive review is presented of Zircaloy microstructure and oxidation characteristics. This information will be used to estimate LOFT peak cladding temperatures by metallographic analysis. Cladding temperatures expected for the LOFT L2-3 and L2-4 tests will be between 1050 and 1400 exp 0 K and their estimations present unique problems in using current metallographic data and techniques. (ERA citation 04:005879)
Postirradiation Metallurgical Techniques to Estimate LOFT Peak Cladding Temperatures
C. S. Olsen (Autor:in)
1978
80 pages
Report
Keine Angabe
Englisch
Reactor Fuels & Fuel Processing , Nonferrous Metals & Alloys , Corrosion & Corrosion Inhibition , Loft reactor , Fuel cans , Microstructure , Temperature gradients , Very high temperature , Zircaloy , ERDA/220600 , Zirconium alloys , Zirconium alloy Zircoloy , Oxidation , Nuclear fuel claddings , Corrosion