• Aucun résultat trouvé

Circumferential fractures

7. SECONDARY FUEL FAILURES

7.5. Circumferential fractures

There is broad agreement in literature that circumferential fractures are the consequence of heavy local hydriding leading to cracks and eventually to rod fractures when pellet cladding contact has been established in an area [7.1].

GE discussed the mechanism in more detail [7.4]. Early life failures should be more susceptible to circumferential fracture due to the still open pellet cladding gap and good communication conditions along the rod, especially when the primary defect is far away from the peak power location, i.e. when the location of heavy secondary hydriding by oxygen starvation coincides with the peak power location where the pellet cladding gap FIG. 7.20. Net increase in tubing diameter for barrier cladding with 100 ppm Fe (“B100”), 400 ppm Fe (“B400”) and non-barrier (NB) cladding [7.49].

FIG. 7.21. Summary of liner oxide thickness data from PIE results published by ABB [7.50], GE [7.51–7.54], INER [7.28] and Siemens [7.55].

closes earliest. This implies that a primary failure at the top more likely leads to fracture, since peak power is usually near the bottom. In fact, circumferential fractures are found in the bottom range, and GE has observed — with a primary failure near the bottom — heavily hydrided cladding in the top range of a rod without fracture, as no pellet clad has contact in this range.

This fully agrees with ABB observations and a similar description in [7.9], as reported circumferential cracks were found in the bottom area in conjunction with debris fretting at a higher axial level. According to Fig. 7.2, the average distance between primary and secondary failure was around two metres, which is quite compatible with oxygen starvation conditions. Of course, one cannot exclude an additional material effect on susceptibility to circumferential cracks, e.g. by the degree of hydrogen pickup and mode of hydriding. However, there is currently no direct evidence for a material effect.

Some years ago, EDF sent a broken fuel rod to hot cell for further examination in order to determine the cause of failure and to explain the fracture mechanism of the fuel rod [7.56]. The rod burnup was about 51 GW◊d/t U.

Metallographic investigations were performed on the axial sample and a radial cut was located close to the rupture.

It was shown that the high burnup rod had initially failed due to grid to rod fretting in the lower part of the rod.

Examinations confirmed that secondary hydriding of the cladding was the cause of these fractures. Severe secondary hydriding of the cladding caused the formation of hydride rings at pellet to pellet interfaces, as shown in Fig. 7.22. At the pellet to pellet interface, cladding areas are typically cooler than in adjacent areas and hydride precipitates preferentially, thus forming hydride rings. The hydride causes severe embrittlement of the cladding, which when then submitted to a stress, has a tendency to break at a pellet to pellet interface.

REFERENCES TO SECTION 7

[7.1] ONOUFRIEV, V., VON JAN, R., “Survey on fuel failures in water cooled power reactors in 1995–98 (CANDUs, BWRs, PWRs, and WWERs)”, IWGFPT/51, IAEA, Vienna (2000).

[7.2] INTERNATIONAL ATOMIC ENERGY AGENCY, Review on Fuel Failures in Water Cooled Reactors, IAEA Technical Reports Series No. 388, IAEA, Vienna (1998).

[7.3] POTTS, G.A., “Recent GE BWR fuel experience”, ANS 1997 Int. Top. Mtg on LWR Fuel Performance, Portland, 1997, ANS, Le Grange, IL, (1997) 261.

[7.4] MONTES, J.A., POTTS, G.A., “Failed fuel degradation”, TopFuel '97 — BNES Conf. Manchester, 1997, p. 5.17.

[7.5] YAGNIK, S.K., et al., “Assessment of BWR fuel degradation by post-irradiation examination and modelling in the defect-code”, ANS 1997 Int. Top. Mtg on LWR Fuel Performance, Portland, 1997, p.329.

[7.6] VESTERLUND, G., HELMERSSON, S., “ABB fuel design and development”, OECD Specialists’ Meeting on Nuclear Fuel and Control Rods, Madrid, 1996, paper 4.A.1.

[7.7] SIHVER, L., et al., “Recent ABB BWR failure experience”, ANS 1997 Int. Top. Mtg on LWR Fuel Performance, Portland, FIG. 7.22. Hydride repartition at a pellet to pellet interface [7.56].

[7.8] LUNABBA, R., MUTTILAINEN, E., “TVO's experience with fuel and control rods”, OECD Specialists' Mtg on Nuclear Fuel and Control Rods, Madrid, 1996, paper 1.4.

[7.9] SIHVER, L., et al., “Recent ABB BWR SVEA fuel failure experience”, TopFuel '97 — BNES Conf., Manchester, 1997, p. 5.1.

[7.10] HÜTTMANN, A., et al., “Post irradiation examination of failed KKK barrier fuel rods”, ANS 1997 Int. Top. Mtg on LWR Fuel Performance, Portland, 1997, p. 350.

[7.11] DANGOULEME , D., Personal communication.

[7.12] KILLEEN, J., Personal communication.

[7.13] EDSINGER, K., “A Review of Fuel Degradation in BWRs”, Proc. of the Int. Top. Mtg on Light Water Reactor Fuel Performance, Park City, 2000, ANS, LaGrange Park, IL (2000).

[7.14] LOCKE, D.H., The behaviour of defective reactor fuel, Nuc Eng and Design 21 (1972) 318–330.

[7.15] DAVIES, J.H., “Secondary damage in LWR fuel following PCI detection — characteristics and mechanisms”, IAEA Spec. Mtg on Behavior of Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, IWGFPT-6, 1980, pp. 135-140:, Chalk River, Ontario, Canada, September 17-20, 1979: Transactions of the ANS, 1982, pp. 269–270.

[7.16] CLAYTON, J.H., “Internal hydriding in irradiated defected zircaloy fuel rods”, 8th Int. Symp. on Zirconium in the Nuclear Industry, STP 1023, (SWAM, L.F.P., EUKEN, C.M., Eds), ASTM, Philadelphia (1989) 266–288.

[7.17] OLANDER, D.R., et al., Chemical processes in defective LWR fuel rods, J Nucl. Mater. 248 (1977) 214–219.

[7.18] ZIMA, G.E., “A Review of the Zircaloy-2 Hydriding Program”, HW-66537 (1960).

[7.19] UNE, K., LESS, J., Common Metals 57 (1978) 93.

[7.20] KIM, Y.S., WANG, W.E., OLANDER, D.R., YAGNIK, S.K., High pressure hydriding of sponge-Zr in steam-hydrogen mixtures, J Nucl. Mater. 246 (1977) 43–52.

[7.21] JONSSON, L., HALLSTATIUS, B., GRAPENGIESSER, M., LYSELL, G., “Failure of a barrier rod in Oskarshamn 3”, Proc.

Int. Top. Mtg on LWR Fuel Performance, ANS, Avignon, 1991, pp. 371–377.

[7.22] TURNAGE, K.G., HUNT, B.E., BENNETT, J.D., GIBSON, E.B., “Fission product analysis and operational experience with leaking fuel rods at the Hatch Nuclear Unit”, Proc. Int. Top. Mtg on LWR Fuel Performance, West Palm Beach, 1994, ANS, La Grange, IL (1994) 467–476.

[7.23] VESTERLUND, G., HELMERSSON, S., “ABB BWR fuel design and development”, 7th Annual Conf., Mexican Nuclear Society (1996) SP15–21.

[7.24] SCHRIRE, G., LYSELL, G., FRENNING, G., RÖNNBERG, L., JONSSON, A., “Secondary defect behavior in ABB BWR fuel,”

Proc. Int. Top. Mtg on LWR Fuel Performance, West Palm Beach, 1994, ANS, La Grange, IL (1994) 398–409.

[7.25] LYSELL, G., GRIGORIEV, V., PETTERSSON, K., “Characteristics of axial splits in failed BWR fuel rods”, 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, ANS/NACE/TMS, 1999.

[7.26] DAVIES, J.H., ARMIJO, J.S., “Post-irradiation examination of failed KKL fuel rods”, KTG Fuel Conference, Karlsruhe, 1993.

[7.27] EDSINGER, K., DAVIES, J.H., ADAMSON, R.B., “Degraded fuel cladding fractography and fracture behaviour”, 12th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1354 (SABOL, G.P., MOAN, G.D., eds) Philadelphia, PA, ASTM, (1999).

[7.28] LIN, K.F., et al., “Investigation on the post-defect deterioration of non-barrier BWR failed rods”, Proc. Int. Top. Mtg on LWR Fuel Performance, West Palm Beach, 1994, ANS, La Grange, IL (1994) 377–390.

[7.29] LYSELL, G., GRIGORIEV, V., EFSING, P., “Axial splits in failed BWR fuel rods”, Proc. of the Int. Top. Mtg on Light Water Reactor Fuel Performance, Park City, 2000, ANS, LaGrange Park, IL (2000).

[7.30] COX, B., Environmentally-induced cracking of zirconium alloys — a review, J Nucl. Mater. 170 (1990) 1–23.

[7.31] MONTGOMERY, R.O., RASHID, Y.R., OZER, O., “Evaluation of post defect fuel behaviour”, Int. Top. Mtg on Light Water Reactor Fuel Performance, West Palm Beach, 1994, ANS, La Grange, IL (1994) 447.

[7.32] WILLIAMS, C.D., et al., 11th ASTM Mtg on Zirconium in the Nuclear Industry, Garmisch, 1996, 676.

[7.33] GRIGORIEV, V., JOSEFSSON, B., ROSBORG, B., “Fracture toughness of Zircaloy cladding tubes”, 11th Int. Symp. on Zirconium in the Nuclear Industry, ASTM STP 2195 (1996) 431–447.

[7.34] EDSINGER, K., DAVIES, J.H., ADAMSON, R. B., “Degraded fuel cladding fractography and fracture behaviour”, ASTM meeting on Zirconium in the Nuclear Industry, Toronto, 1998.

[7.35] LYSELL, G., GRIGORIEV, V., “Characteristics of axial splits in failed BWR fuel rods”, 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, TMS, Newport Beach, 1999.

[7.36] DUTTON, R., PULS, M.P., “A theoretical model for hydrogen induced sub-critical crack growth”, Effects of Hydrogen on Behaviour of Materials, AIME (1976) 516–525.

[7.37] EADIE, R.L., SMITH, R.R., “Modelling delayed hydride cracking in Zirconium alloys”, Can. Metall. Q. 27 (1988) 213–223.

[7.38] NUTTALL, K., ROGOWSKI, A.J., Some fractographic aspects of hydrogen-induced delayed cracking in Zr-2.5 wt% Nb alloys, J. Nucl. Mater. 80 (1979) 279–290.

[7.39] McMINN, E.C., DARBY, SCHOFIELD, J.S., “Terminal solubility of hydrogen in Zirconium alloys”, 12th Int. Symp. on Zirconium in the Nuclear Industry, ASTM STP 1354, (SABOL, G.P., MOAN, G.D., Eds) Philadelphia, PA, ASTM (1999).

[7.40] EFSING, P., PETTERSSON, K., “The influence of temperature and yield strength on delayed hydride cracking in hydrided Zircaloy-2”, Zirconium in the Nuclear Industry, ASTM STP 1295 (BRADLEY, E.R., SABOL, G.P., Eds.) ASTM (1996) 394–404.

[7.41] EFSING, P., PETTERSSON, K., “Delayed hydride cracking in irradiated Zircaloy cladding”, 12th Int. Symp. on Zirconium in the Nuclear Industry, ASTM STP 1354 (SABOL, G.P., MOAN, G.D., Eds.) Philadelphia, PA, ASTM (1999).

[7.42] EFSING, P., “Delayed hydride cracking in irradiated Zircaloy”, PhD thesis, KTH, Stockholm (1998).

[7.43] EDSINGER, K., VAIDYANATHAN, S., ADAMSON, R.B., “On the mechanism of axial splits in failed BWR fuel rods”, 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 1999, ANS/NACE/TMS.

[7.44] SHI, S.-Q., SHEK, G.K., PULS, M.P., Hydrogen concentration limit and critical temperatures for delayed hydride cracking in Zirconium alloys, J. Nucl. Mater. 218 (1995) 189–201.

[7.45] GRIGORIEV, V., JOSEFSSON, B., On the mechanism of Zircaloy cladding axial splits, J. Nucl. Mater. 257 (1998) 99–107.

[7.46] GRIGORIEV, V., PETERSSON, K., “On the indications of shear fracture at the tip of an axial notch in Zircaloy cladding”, 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, TMS, Newport Beach, 1999.

[7.47] DAVIES, J.H., POTTS, G.A., “Post-defect behavior of barrier fuel”, Proc. Int. Top. Mtg on LWR Fuel Performance, Avignon, 1991, ANS, La Grange, IL, (1991) 272–284.

[7.48] ARMIJO, J.S., “Performance of failed BWR fuel”, Proc. Int. Top. Mtg on LWR Fuel Performance, West Palm Beach, 1994, ANS, La Grange, IL (1994) 410–422.

[7.49] EDSINGER, K., unpublished work, Vallecitos Nuclear Center, 1998.

[7.50] LYSELL, G., SCHRIRE, D., SIHVER, L., “Disposition of oxygen and hydrogen arising from water ingress in a failed Sn-alloy Zirconium liner fuel rod”, HPR-349, 1998.

[7.51] DAVIES, J.H., HOSHI, E.V., REAGER, R.D., ZIMMERMAN, D.L., WARNER, R.W., “Post-irradiation evaluation of BWR fuel from the Hatch-1 Reactor — Final Report”, EPRI TR-106036 (1995).

[7.52] DAVIES, J.H., HOSHI, E.V., REAGER, R.D., ZIMMERMAN, D.L., WARNER, R.W., “Post-irradiation evaluation of BWR fuel from Hope Creek Reactor”, EPRI TR-106348 (1996).

[7.53] EDSINGER, K.W., DAVIES, J.H., FARKAS, D.M., REAGER, R.D., HOSHI, E.V, internal GE report (1997).

[7.54] SCHLEUNIGER, P., et al. internal GE/PSI report (1994).

[7.55] HÜTTMANN, M., et al., “Post-irradiation examination of failed KKK-barrier fuel rods”, Proc., Int. Top. Mtg on LWR Fuel Performance, Portland, 1997, ANS, La Grange, IL (1997) 350–355.

[7.56] BOURGOIN, J.,VAN SWAM, L.F., BOURNAY, P., “Hot cell analysis of fuel rod fractured during handling in the pool”, Colloque de FONTREVAUD III.

8. FUEL FAILURE PREVENTION AND