Corrosion in pressurized water reactors (PWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 11

11. J. Lumsden and A. McIlree , 'Factors affecting PBSCC in alloy 600 and alloy 690

steam generator tubing,' International symposium , Fontevraud VI ( France ),
2006 .

12. R.T. Begley , A.W. Klein and R.E. Gold , 'Investigations of ID stress corro-

sion cracking in fi eld and laboratory programs,' International symposium,
Fontevraud ( France ), 1985 .

13. F. Cattant and F. de Keroulas , 'Examens des tubes en alliage 600 extraits des

générateurs de vapeur des centrales EDF,' International symposium, Fontevraud
( France ), 1985 .

14. C. Bibollet , C. Beroni, S. Raimbault, M. Stindel, N. Verdiere and J.-P. Gauchet,

'EDF fi eld experience on steam generator divider plate examinations,'
Fontevraud 6, 2006.

15. D. Deforge, L. Duisabeau, S. Miloudi, Y. Thebault, T. Couvant, F. Vaillant and E.

Lemaire, 'Learning from EDF investigations on SG divider plates and vessel
head nozzles. Prior deformation effect on stress corrosion cracking,' Fontevraud
7, Avignon (France), 2010.

16. F. Vaillant, S. Le Hong, C. Amzallag and C. Bosch, 'Crack growth rates on vessel

penetrations in alloy 600 in primary water,' Fontevraud 4, 1998.

17. F. Vaillant et al ., 'Crack growth rates in thick materials of alloy 600 and weld

metals of alloy 182 in laboratory primary water. Comparison with fi eld experi-
ence,' Fontevraud 5, 2002.

18. T. Couvant , F. Vaillant and E. Lemaire , 'Stress corrosion crack growth rate

in rolled alloy 600 exposed to primary PWR environment,' Proceedings of
14th International Symposium on Environmental Degradation of Materials in
Nuclear Power Systems-Water Reactors , Virginia Beach ( Virginia ), 2009 .

19. T. Couvant , S. Miloudi , F. vaillant , D. Déforge , Y. Thébault , 'PWSCC of steam

generator divider plates in alloy 600: coupling fi eld characterizations with R&D
studies,' Proceedings Fontevraud 7, International Symposium Contribution of
Materials Investigations to the Resolution of Problems Encountered in PWR ,
SFEN , 2010 .

20. T. Couvant , P. Moulart , L. Legras , P. Bordes , J. Capelle , Y. Rouillon , T. Balon ,

'PWSCC of austenitic stainless steels of heaters of pressurizers,' Fontevraud 6,
2006 .

21. Y. Thébault , P. Moulart , K. Dubourgnoux , J. Champredonde , T. Couvant , Y. Neau ,

J.M. Fageon , D. Lecharpentier , A. Breuil , V. Derouet , 'PWSCC of Thermocoax
Pressurizer Heaters in Austenitic Stainless Steel and Remedial Actions to pre-
venting SCC,' 15th International Conference on Environmental Degradation
of Materials in Nuclear Systems-Water Reactors , Colorado Springs ( Colorado ),
2011 .

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22. T. Couvant , L. Legras , F. Vaillant , J.M. Boursier , Y. Rouillon , 'Effect of

strain-hardening on stress corrosion cracking of AISI 304 L stainless steel in
PWR environment at 360°C,' 12th International Conference on Environmental
Degradation of Materials in Nuclear Systems-Water Reactors , Snowbird ( Utah ),
2005 .