Experimental study of steam convective cooling effect on Zr cladding oxidation phenomena at 900℃

Author:

Seo Siwon,Fredi Simamora Benrico,Young Lee Jae

Funder

Korea Hydro and Nuclear Power

Publisher

Elsevier BV

Reference22 articles.

1. “Nuclear safety in light water reactors;Sehgal,2012

2. severe accident research network of excellence”;Albiol;Prog. Nucl. Energy,2010

3. M. L. CARBONEAU, “Highlights of the OECD-LOFT LP-FP-2 Experiment, Including Hydrogen Generation, Fission Product Chemistry, and Transient Fission Product Release Fraction,” Proc. OECD/LOFTMtg., Madrid, Spain, May 9-11, 1990, Organisation for Economic Cooperation and Development (1990).

4. Hydrogen generation behavior in the LOFT FP-2 and other experiments: comparative assessment for mitigated severe accident conditions;Cronenberg;Nucl. Technol.,1992

5. J. Stuckert, M. Steinbruck, U. Stegmaier, “Sing rod Quench tests with Zr-1Nb cladding. Comparison with Zircaloy-4 cladding tests and modeling”, Report FZKA-6604, Karlsruhe Institute of Technology (2001).

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