Comments to papers of J.H. Kim et al. [1] and M. Große et al. [2] recently published in JNM "On the hydrogen uptake of Zircaloy-4 and M5™ alloys subjected to steam oxidation in the 1100-1250 °C temperature range"

Journal of Nuclear Materials

Volumn 395, Issue 1-3, 2009, Pages 169-172

  Brachet, J C ^a   Vandenberghe, V ^a  

^a CEA SACLAY   (France)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 70449715096     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2009.09.017     Document Type: Letter

References (18)

1. Kim J.H., Lee M.H., Choi B.K., and Jeong Y.H. Journal of Nuclear Materials 362 (2007) 36-45
2. Große M., Lehmann E., Steinbrück M., Kühne G., and Stuckert J. Journal of Nuclear Materials 385 (2009) 339-345
3. L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev, V. Smirnov, V. Chesanov, A. Goryachev, Experimental Study of Embrittlement of Zr-1%Nb VVER Cladding under LOCA-Relevant Conditions, NUREG/IA-0211/IRSN 2005-194/NSI RRC KI 3188 Report, 2005.
4. M. Billone, Y. Yan, T. Burtseva, Cladding Embrittlement during Postulated Loss-of-Coolant Accidents, ANL NUREG/CR-6967 Report, ML082130389, 2008-07-31.
5. Hozer Z., Gyori C., Matus L., and Horvath M. Journal of Nuclear Materials 373 (2008) 415-423
6. Nagase F., and Fuketa T. Journal of Nuclear Science Technology 42 2 (2005) 209-218
7. ™ (Zr-NbO) alloys after oxidation at 1100 °C and quenching, in: Proceeding of TCM on Fuel behavior under Transient and LOCA Conditions Organised by IAEA, Halden, September 10-14, 2001.
8. Portier L., Bredel Th., Brachet J.-C., Maillot V., Mardon J.-P., and Lesbros A. Journal of ASTM International 2 2 (2005) Paper ID JAI12468
9. ™ and Zircaloy-4 alloys under LOCA conditions, in: 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005, Proceeding ICONE13-50457.
10. Brachet J.-C., Vandenberghe-Maillot V., Portier L., Gilbon D., Lesbros A., Waeckel N., and Mardon J.-P. Journal of ASTM International 5 5 (2008) Paper ID JAI101116
11. ™: experience feedback and understanding of phenomenological aspects, in: Proceeding of 2008 Water Reactor Fuel Performance Meeting, October 19-23, 2008, Seoul, Korea.
12. C. Grandjean, G. Hache, A State-Of-The-Art-Report of Past Programmes Devoted to Fuel Behaviour Under Loss-Of-Coolant Conditions - Part 3 - Cladding Oxidation, Resistance to Quench and Post-Quench Loads, DPAM/SEMCA 2008-093 IRSN Technical Report, June 2008.
13. Böhmert J., Dietrich M., and Linek J. Nuclear Engineering and Design 147 (1993) 53
14. Furuta T., and Kawasaki S. Journal of Nuclear Materials 105 (1982) 119-131
15. Uetsuka H., Furuta T., and Kawasaki S. Journal of Nuclear Science and Technology 19 2 (1982) 158-165
16. Uetsuka H., and Otomo T. Journal of Nuclear Science and Technology 26 2 (1989) 240-248
17. ™), in: Proceeding of the SEGFSM-Topical Meeting on LOCA, May 24-26, 2004, Argonne National Lab., Chicago, USA.
18. M. Billone, Private communication - Data to be published (available upon request), ANL, 2009.