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KEYWORD_EN:Zirconium dioxide 10 result(s) found
 
1. HEAT-UP AND COOL-DOWN TEMPERATURE-DEPENDENT HYDRIDE REORIENTATION BEHAVIORS IN ZIRCONIUM ALLOY CLADDING TUBES

Won, Ju-Jin;Kim, Myeong-Su;Kim, Kyu-Tae;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 681-688
 
2. RADIATION-INDUCED DISLOCATION AND GROWTH BEHAVIOR OF ZIRCONIUM AND ZIRCONIUM ALLOYS – A REVIEW

CHOI SANG IL ; KIM JI HYUN
Nuclear Engineering and Technology, vol. 45, iss. 3, 2013, pp. 385-392
 
3. Synthesis, Characterization and Antimicrobial Activity of Zirconium (IV) Complexes

Shobhana Sharma;Asha Jain;Sanjiv Saxena;
Journal of the Korean Chemical Society, vol. 56, iss. 4, 2012, pp. 440-447
 
4. ANALYSIS OF EQUILIBRIUM METHODS FOR THE COMPUTATIONAL MODEL OF THE MARK-IV ELECTR OREFINER

Cumberland, Riley;Hoover, Robert;Phongikaroon, Supathorn;Yim, Man-Sung;
Nuclear Engineering and Technology, vol. 43, iss. 6, 2011, pp. 547-556
 
5. OUT-OF-PILE MECHANICAL PERFORMANCE AND MICROSTRUCTURE OF RECRYSTALLIZED ZR-1.5 NB-O-S ALLOYS

Ko, S.;Lee, J.M.;Hong, S.I.;
Nuclear Engineering and Technology, vol. 43, iss. 5, 2011, pp. 421-428
 
6. PROPERTIES OF ZR ALLOY CLADDING AFTER SIMULATED LOCA OXIDATION AND WATER QUENCHING

Kim, Hyun-Gil;Kim, Il-Hyun;Jung, Yang-Il;Park, Jeong-Yong;Jeong, Yong-Hwan;
Nuclear Engineering and Technology, vol. 42, iss. 2, 2010, pp. 193-202
 
7. HIGH BURNUP FUEL ISSUES

Rudling, Peter;Adamson, Ron;Cox, Brian;Garzatolli, Friedrich;Strasser, Alfred;
Nuclear Engineering and Technology, vol. 40, iss. 1, 2008, pp. 1-8
 
8. COATED PARTICLE FUEL FOR HIGH TEMPERATURE GAS COOLED REACTORS

Verfondern, Karl;Nabielek, Heinz;Kendall, James M.;
Nuclear Engineering and Technology, vol. 39, iss. 5, 2007, pp. 603-616
 
9. Characterization of Zirconium Sulfate Supported on Zirconia and Activity for Acid Catalysis

Son, Jong Rak;Gwon, Tae Dong;Kim, Sang Bok;
Bulletin of the Korean Chemical Society, vol. 22, iss. 12, 2001, pp. 1309-1315
 
10. Effect of Alloying Elements on the Thermal Creep of Zirconium Alloys

Cheol Nam;Kim, Kyeong-Ho;Lee, Myung-Ho;Jeong, Yong-Hwan;
Nuclear Engineering and Technology, vol. 32, iss. 4, 2000, pp. 372-378
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