The aim of the paper is to introduce methods to estimate the residual life of steam generators with alloy 600 thermally treated (TT) tubing, taking into account primary water stress corrosion cracking (PWSCC) as the main contributor damage. The methods take into account both initiation and propagation of PWSCC cracks in the expansion transition zone of steam generator tubes, as well as the current damage status (cracking and plugging) of the tube bundle, known from inspection results. A probabilistic model is used to treat initiation, while the propagation stage is treated in a deterministic way based on inspection data. After introducing the methods used to assess the residual life, a brief parametric study will be shown to illustrate the effects of initiation versus propagation. Eventually, the cases of a few actual steam generators with tubing made of alloy 600 TT showing different situations of present damage and damage evolution rates will be presented.

1.
IAEA
, 2008, “
Heavy Component Replacement in Nuclear Power Plants: Experience and Guidelines
,” IAEA Nuclear Energy Series Paper No. NP-T-3.2.
2.
NRC
, 2008, NRC information letter in 2008–2007.
3.
Saint-Paul
,
P.
, and
Slama
,
G.
, 1991, “
Steam Generator Materials Degradations
,”
Proceedings of the Fifth Environmental Degradation Conference
, NACE, pp.
39
49
.
4.
Staehle
,
R. W.
,
Gorman
,
J. A.
,
Stavropoulos
,
K. D.
, and
Welty
,
C. S.
, Jr.
, 1994, “
Application of Statistical Distributions to Characterizing and Predicting Corrosion of Tubing in Steam Generators of Pressurized Water Reactors
,”
Life Prediction in Corrodible Structures Conference
,
NACE and JSCE Conference
,
R.
Parkins
, ed.,
NACE International
,
Houston, TX
, pp.
1374
1439
.
5.
Scott
,
P. M.
, and
Benhamou
,
C.
, 2002, “
An Overview of Recent Observations and Interpretations of IGSCC in Nickel Base Alloys in PWR Primary Water
,”
Proceedings of the Tenth Environmental Degradation Conference
,
NACE
, Lake Tahoe.
6.
Scott
,
P. M.
,
Benhamou
,
C.
, and
Meyzaud
,
Y.
, 1995,
Plant Ageing and Life Prediction of Corrodible Structures
,
NACE Conference
,
T.
Shoji
and
T.
Shibata
, eds.,
NACE
,
Sapporo, Japan
, pp.
285
294
.
7.
Benhamou
,
C.
, and
Amzallag
,
C.
, 2008, “
Implementation of Monte-Carlo Methodology to Predict Stress Corrosion Initiation Time of Alloy 600 PWR Components
,”
International Conference on SCC Initiation in Nuclear Power Plants
, Beaune, France.
8.
de Curières
,
I.
, and
Meunier
,
M. C.
, 2008, “
Prediction of PWSCC Initiation in Steam Generator Alloy 600 Tubes by the Index Model: Comparison Between Model and Experience
,”
International Conference on SCC Initiation in Nuclear Power Plants
, Beaune, France.
9.
Scott
,
P. M.
, 1991 “
An Analysis of Primary Water Stress Corrosion Cracking in PWR Steam Generators
,”
Specialist Meeting on Operating Experience With Steam Generators
, UNIPEDE, Brussels, Belgium, Paper Nos. 5–6.
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