Corrosion in pressurized water reactors (PWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 10

microstructures. In particular, experience in the fi eld demonstrated that an
increase in chromium content is an effi cient strategy: to date nickel alloys
containing 30% chromium, used to replace 16% chromium nickel alloys,
have exhibited very good resistance to localized corrosion, such as SCC. The
history of the degradations shows that for a given type of material, the ten-
dency to corrode can largely depend on the manufacturing conditions.

2.5 References
1 . H . X u , S . F y fi tch , J.W. Hyres , T.A. Lang and T.T. Pleune , 'Laboratory investigation
of PWSCC of CRDM nozzle 3 and its J-Groove weld on the Davis-Besse reac-
tor vessel head,' Proceedings of 12th International Conference of Environmental
Degradation of Materials in Nuclear Power Systems - Water Reactors , The
Minerals, Metals and Materials Society, 2005.
2 . H . X u , S . F y fi tch and J.W. Hyres , 'Laboratory investigation of the stainless steel
cladding on the Davis-Besse reactor vessel head,' Proceedings 12th International
Conference of Environmental Degradation of Materials in Nuclear Power
Systems - Water Reactors , The Minerals , Metals and Materials Society , 2005 .
3. R. Cauvin , O. Goltrant , Y. Rouillon , E. Verzaux , A. Cazus , P. Dubuisson , P.
Poitrenaud and S. Bellet , 'Endommagement des structures internes inférieures
soumises à fortes fl uences: apports de l'expertise,' International Symposium,
Fontevraud III ( France ), 1994 .
4. O. Goltrant , R. Cauvin , D. Deydier and A. Trenty , 'Eléments internes inférieurs:
apports de l'expertise d'une cornière de Chooz A,' International Symposium,
Fontevraud III ( France ), 1994 .
5. I. Monnet , G.M. Decroix , P. Dubuisson , J. Reuchet and O. Morlent , 'Investigation
of the Chooz A nuclear power plant bolts,' International Symposium, Fontevraud
IV ( France ), 1998 .
6. C. Pokor , G. Courtemanche , JL. Fléjou , M. Tommy-Martin , I. Rupp , B. Tanguy ,
J.-P. Massoud and N. Monteil, 'IASCC of core internals of PWRs: EDF R&D and
engineering program to assess internals lifetime management,' International
Symposium , Fontevraud VII ( France ), 2010 .
7. NRC information notice 2006-08: secondary piping rupture at the Mihama
power station in Japan, March 2006.

￿ ￿ ￿ ￿ ￿ ￿

8. J.M. Boursier , P. Jardet , F. de Keroulas , P. Lemaire and Y. Rouillon , 'Contribution

des expertises metallurgiques de tubes extraits à la comprehension de la corro-
sion en milieu secondaire des générateurs de vapeur REP d'EDF,' International
symposium , Fontevraud IV ( France ), 1998 .

9. J.M. Boursier , M. Dupin , P. Gosset and Y. Rouillon , 'Secondary side corrosion

of French PWR steam generator tubing: contribution of the surface analyses to
the understanding of the degradation process,' Proceedings of 9th International
Symposium on Environmental Degradation of Materials in Nuclear Power
Systems-Water Reactors , 1999 .

10. A. McIlree , K. Fruzzetti , J. Gorman , W. Shack , R. Staehle and J. Stevens , 'A

case of the major infl uence of lead and sulfur in the secondary side degrada-
tion of PWR steam generators tubing,' International symposium, Fontevraud
VI ( France ), 2006 .