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Remaining Time Assessment of the Steam Generator Welding Joint № 111-1 of NPP VVER-1000 with Respect to Detected Cracks. Professor V.I. Makhnenko, scientist A.S. Milenin E.O. Paton Electric Welding Institute of National Academy of Sciences of Ukraine. 1.
Professor V.I. Makhnenko, scientist A.S. Milenin
E.O. Paton Electric Welding Institute
of National Academy of Sciences of Ukraine
body of steam generator;
pipe conduit DU-850;
A discontinuity (defect).
Fig. 2. Defectogram of the welded joint №111-1 of “hot” collector 1PG-1 of Uzhno-Ukrainskaya nuclear power-plant in ~1 year after first repair.
Fig. 4. Cartogram of discontinuity №3 of the welded joint №111-1 (“hot” collector) PG-3 of power unit №4 Zaporozhskaya nuclear power-plant according to the data of the Expert's report “UkrTsNIITMASh” of 13.01.2006.
Questions are to be answered: 1. What is the degree of risk of the generation of the through-wall crack within the mentioned period of the exploitation, i.e. the leakage in the region of the growing defect, that will lead to the emergency stop of the power unit?
2. What is the degree of risk of the spontaneous destruction with the unpredictable consequences?
MainProblem: permissibility of exploitation of the steam generator 4PG-3 of Zaporozhskaya nuclear power-plant with a detected defect in the region of the welded joint №111-1 until at least the next planned repair(about 1 year).
Fig. 5. Calculation data about the distribution of working stresses szz in the region of the pocket depending on pressure in the steam generator P=6.4 MPa and in the collector PC=16 MPa.
Fig. 7. Scheme of the diagram of the static corrosive crack growth resistance of constructional material:
diagram lg v – KI according to experimental data;
Three main stages of the diagram of the static corrosive crack growth resistance:
Calculation of the coefficient of stress intensity KI(D), KI(G) and sref for the semi-elliptical crack a×2c.
If (a/c)<1.0 and (a/d)<0.7
Sjis an equivalent stress
Here szz(i) is total stress szz according to the diagram in Fig. 6 at the depth (a/20)·i (i=0,1,2,…,20); Ci, Di, Ei, Fi are tabulated weighting functions,
, if Lr < Lrmax
Kr=0, if Lr ≥ Lrmax
sref is the stress that is determined with external power load without taking into account the residual stresses and that is able at some level of the loading to cause the plastic collapse in the region of the defect under consideration.
Fig. 9. Kinetics of reducing of the safety factor against spontaneous growth of crack a0=40 mm, c0=45 mm in time: KISCC=10 MPa·m1/2, vm=44 mm/year.
Conclusions: 1. Numerical analysis of state of the steam generator 4PG-3 of Zaporozhskaya nuclear power-plant showed that the risk of leakage (through defect) in the course of year of its exploitation (with double time reserve) is obviously absent.
2. The kinetics of the changing of safety factor against the spontaneous propagation of crack showed that during a year of the exploitation the risk of such a spontaneous growth is minimal.