A physically and statistically based method for steam generator (SG) heat exchanger tubes (HET) integrity assessment is proposed. The method based is on the stochastic laws of crack dimensions distribution with taking into account its growth, limit load-model of cracked tube, and SG plugging statistics. Based on the history of the tubes, plugging of the specific SG three statistical parameters has to be found: initial number of defects, stochastic parameter of defect depth, and the defect growth rate. The developed method was used for the prediction of HET failure for all Ukrainian SG. It is also used for the justification of pressure reduction of hydrostatic test (HT) for primary circuit of WWER NPPs. It is shown that the pressure reduction from 24.5 to 19.6 MPa for WWER-1000 s and from 19.1 to 15.7 MPa for the WWER-440 s does not practically increase the HET failure probability during operation.

References

1.
Bergunker
,
V. D.
,
Trunov
,
N. B.
, and
Denisov
,
V. V.
,
2004
, “
Analysis of WWER SG Condition According to the ECT Data
,”
6th International Seminar on Horizontal Steam Generators
, Podolsk, Russian Federation,
15
p. (in Russian).
2.
NNEGC
,
2014
, “
An Analysis of Current Criteria on the Number of Plugged Heat Exchanger Tubes of Steam Generators of Ukrainian NPPs,” SS STC NNEGC “Energoatom
,” Technical Report, Kyiv, Russia, p. 77 (in Russian).
3.
Lin
,
L.
,
Cragnolino
,
G.
,
Szklarska-Smialovska
,
Z.
, and
Macdonald
,
D.
,
1981
, “
Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel in High Temperature Cloride Solutions
,”
Corrosion
,
37
(
11
), pp.
616
627
.
4.
Diercks
,
D. R.
,
Bakhtiari
,
S.
,
Kasza
,
K. E.
,
Kupperman
,
D. S.
,
Majumdar
,
S.
,
Park
,
J. Y.
, and
Shack
,
W. J.
,
1999
, “
Steam Generator Tube Integrity Program
,” Technical Report, NUREG/CR-6511, Vol. 6, U.S. NRC, Washington, DC,
Report No. ANL-99/8
.
5.
IAEA
,
2011
, “
Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators
,” IAEA, Vienna,
Standard No. IAEA-TECDOC-1668
.
6.
Vlasenko
,
N. I.
, and
Kozlov
,
V.
,
2006
, “
Efficiency of The Safety Enhancement Measures Provided For Steam Generators PGV-1000M at Ukraine NPPs
,”
7th International Seminar on Horizontal Steam Generators, Podolsk, Russian Federation
,
18
p. (in Russian).
7.
IAEA
,
2007
, “
Strategy for Assessment of WWER Steam Generator Tube Integrity
,” IAEA, Vienna,
Standard No. IAEA-TECDOC-1577
.
8.
NNEGC
,
2006
, “
Sectoral Technical Decision by Volume and Frequency of PGV-1000 Heat Exchanger Tubes Monitoring in the Ukrainian NPPs
,” NNEGC “Energoatom,” Kyiv, Russia, Regulation No. TR-N.1.2.3.4.095–06 (in Russian).
9.
OKB GIDROPRESS
,
2000
, “
Steam Generator PGV-1000M With Supports. Technical Description and Operating Manual
,” Podolsk, Russian Federation (in Russian), Regulation No. 320.05.00.00.000 ТО.
10.
Orynyak
,
I.
,
Zarazovskii
,
M.
,
Batura
,
A.
,
Borodii
,
M.
, and
Danil'chuk
,
E.
,
2014
, “
Brittle Fracture Probabilistic Assessment of WWER-1000 RPVs
,”
ASME
Paper No. PVP2014-28557.
11.
Orynyak
,
I. V.
, and
Ageev
,
S. M.
,
2009
, “
Modelling the Limiting Plastic State of Heavy-Walled Pipes With Axial Surface Defects
,”
J. Mach. Manuf. Reliab.
,
38
(
4
), pp.
407
413
.
12.
Orynyak
,
I.
,
Ageev
,
S.
,
Radchenko
,
S.
, and
Zarazovskii
,
M.
,
2015
, “
Local Limit Load Analytical Model for Thick-Walled Pipe With Axial Surface Defect
,” J. Pressure Vessel. Technol.,
137
(
5
),
ASME
Paper No. PVT-14-1097.
13.
Kiefner
,
J. F.
,
Maxey
,
W. A.
,
Eiber
,
R. J.
, and
Duffy
,
A. R.
,
1973
, “
Failure Stress Levels of Flaws in Pressurized Cylinders
,”
Progress in Flaw Growth and Fracture Toughness Testing
, ASTM STP 536, pp.
461
481
.
14.
Folias
,
E. S.
,
1967
, “
A Circumferential Crack in a Pressurized Cylindrical Shell
,”
Int. J. Fract. Mech.
,
3
(
1
), pp.
1
11
.
15.
Schuster
,
G. J.
,
Doctor
,
S. R.
, and
Heasler
,
P. G.
,
2008
, “
Characterization of Flaws in U.S. Reactor Pressure Vessels. Density and Distribution of Flaw Indications in PVRUF
,” Technical Report, NUREG/CR-6471, Vol. 1, U.S. NRC, Washington, DC, Report No. PNNL-11143.
16.
Khaleel
,
M. A.
, and
Simonen
,
F. A.
,
2009
, “
Evaluations of Structural Failure Probabilities and Candidate Inservice Inspection Programs
,” Technical Report, NUREG/CR-6986, U.S. NRC, Washington, DC,
Report No. PNNL-13810
.
17.
Orynyak
,
I.
,
Kozlov
,
V.
,
Borodii
,
M.
, and
Zarazovskii
,
M.
,
2015
, “
Application of the Structural Reliability Methods for Justification of Pressure Reduction of Periodic Hydrostatic Test for Primary Circuit of NPP WWER-1000
,”
ASME
Paper No. PVP2015-45573.
18.
EPRI
,
1999
, “
Revised Risk-Informed Inservice Inspection Evaluation Procedure (PWRMRP-05)
,” Electric Power Research Institute, Topical Report, Project No. 669, Palo Alto, CA,
Report No. TR-112657
.
19.
Orynyak
,
I. V.
,
Yakovleva
,
E. S.
, and
Dubik Ya
,
R.
,
2012
, “
The Application of the Combined Method of Weight Functions for the Determination of a Through-Wall Crack Opening Area in a Shell
,”
Strength of Materials
,
44
(
6
), pp.
600
616
.
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