Abstract
Data for the fracture strength of embedded hydride precipitate clusters in zirconium and its alloys are reviewed and the results analyzed. Fracture strength values are derived from two types of tests. One type involves determining fracture initiation in hydrides in rising load tensile tests of zirconium material of different strengths and microstructures containing a uniform distribution of radial (perpendicular) hydride clusters. In these tests, fracture initiation is determined either by Acoustic Emission (AE) or monitored with a high intensity source of synchrotron X-rays. Another type of test involves growing long hydrided regions from planar surfaces of cantilever beam specimens loaded in bending under a series of constant loads to determine the lowest applied load at which such hydrided regions fracture and DHC is initiated. The lower bound fracture strength value consistent with the results obtained from the complete data set of these two types of tests is 450 MPa. This result is limited to embedded hydride clusters in unirradiated or pre-irradiated Zr–2.5Nb pressure tube material oriented such that their long dimensions are perpendicular to the applied load.
Keywords
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.
This is a preview of subscription content, log in via an institution.
Buying options
Tax calculation will be finalised at checkout
Purchases are for personal use only
Learn about institutional subscriptionsNotes
- 1.
An experimental cold worked Zr–Nb pressure tube material that was never used in practice.
- 2.
It should be noted that lattice parameter measurements of the γ-hydride phase can only approximately be of its stress-free state since bulk specimens consisting only of the γ phase—and therefore unconstrained by a misfitting surrounding phase—have never been produced, a point that was also recognized by Steuwer et al. [48].
References
Arsène, S., Bai, J.B., Bombard, P.: Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part I. Hydride embrittlement in stress-relieved, annealed, and recystallized ZIRCALOYs at 20 °C and 300 °C. Metall. Trans. A 34A, 553–566 (2003)
Arsène, S., Bai, J.B., Bombard, P.: Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part III. Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C. Metall. Trans. A 34A, 579–588 (2003)
Bai, J.B., Prioul, C., François, D.: Effect of microstructure factors and cold-work on the hydride precipitation in Zircaloy-4. J. Adv. Sci. 3, 188–200 (1991)
Bai, J.B., Prioul, C., François, D.: Hydride embrittlement in ZIRCALOY-4 plate: Part I. Influence of microstructure on the hydride embrittlement in ZIRCALOY-4 at 20 °C and 350 °C. Metall. Trans. 25A, 1185–1197 (1994)
Bai, J.B., Ni, J., Prioul, C., et al.: Hydride embrittlement in ZIRCALOY-4 plate: Part III. Interaction between tensile stress and the hydride morphology. Metall. Trans. A25A, 1199–1208 (1994)
Bai, J.B.: Effect of hydriding temperature and strain rate on the ductile-brittle transition in β treated Zircaloy-4. J. Nucl. Sci. Technol. 33, 141–146 (1996)
Barraclough, K.G., Beevers, C.J.: Some observations on the deformation characteristics of bulk polycrystalline zirconium hydrides—part I. The deformation and fracture of hydrides based on the δ-phase. J. Mater. Sci. 4, 518–525 (1969)
Beremin, F.M.: Cavity formation from inclusions in ductile fracture of A508 steel. Metall. Trans. A 12A, 723–731 (1981)
Berveiller, M., Zaoui, A.: An extension of the self-consistent scheme to plastically-flowing polycrystals. J. Mech. Phys. Solids 26, 325–344 (1979)
Bourcier, R.J., Koss, D.A.: Hydrogen embrittlement of titanium sheet under multiaxial states of stress. Acta Metall. 32, 2091–2099 (1984)
Cassidy, M.P., Wayman, C.M.: The crystallography of hydride formation in zirconium: I. The δ → γ transformation. Metall. Trans. A 11A, 47–56 (1980)
Cheadle, B.A., Ells, C.E.: Crack initiation in cold-worked Zr-2.5 wt percent Nb by delayed hydrogen cracking. In: Proceedings of 2nd International Congress on Hydrogen in Metals. Pergamon, Oxford, Paper C38 (1977)
Cheadle, B.A., Coleman, C.E., Ells, C.E.: Prevention of delayed hydride cracking in zirconium alloys. In: Adamson, R.B., Van Swam, L.F.P. (eds.) Zirconium in the Nuclear Industry: Seventh International Symposium. ASTM STP, vol. 939, pp. 224–240 (1987)
Choubey, R., Puls, M.P.: Crack initiation at long radial hydrides in Zr–2.5Nb pressure tube material at elevated temperatures. Metall. Trans. A 25A, 993–1004 (1994)
Coleman, C.E., Hardie, D.: The hydrogen embrittlement of α-zirconium—A review. J. Less-Common Met. 2, 168–185 (1966)
Coleman, C.E., Ambler, J.F.R.: Delayed hydrogen cracking in Zr–2.5Nb alloy. Rev. Coat. Corros. III (2 and 3), 105–157 (1979)
CSA: Technical Requirements of the In-service Evaluation of Zirconium Alloy Pressure Tubes in CANDU Reactors. Canadian Standards Association, Mississauga, Ontario, Canada, Nuclear Standard N285.8-10 (2010)
Cox, H.L.: The elasticity and strength of paper and other fibrous materials. Br. J. Appl. Phys. 3, 72–79 (1952)
Cui, J., Shek, G.K., Scarth, D.A., et al.: Delayed hydride cracking initiation at notches in Zr–2.5Nb pressure tube material. J. Press. Vess. Technol. 131, 041407 (2009)
Cui, J.: Unpublished. Kinectrics Inc., Toronto, Ontario, Canada (2003)
Dutton, R., Nuttall, K., Puls, M.P., et al.: Mechanisms of hydrogen induced delayed cracking in hydride forming materials. Metall. Trans. A 8A, 1553–1562 (1977)
Ells, C.E.: Hydride precipitates in zirconium alloys. J. Nucl. Mater. 28, 129–151 (1968)
Eshelby, J.D.: The determination of the elastic field of an ellipsoidal inclusion, and related problems. Proc. R. Soc. London A 241, 376–396 (1957)
Eshelby, J.D.: Elastic inclusions and inhomogeneities. Prog. Sol. Mech. 2, 89–140 (1961)
Eshelby, J.D.: Continuum theory of lattice defects. In: Seitz, F., Turnbull, D. (eds.) Solid State Physics, vol. 3, pp. 79–140. Academic, New York (1966)
Evans, W., Parry, G.W.: The deformation behaviour of Zircaloy-2 containing directionally oriented zirconium hydride precipitates. Electrochem. Technol. 4, 225–231 (1966)
Hardie, D.: The influence of the matrix on the hydrogen embrittlement of zirconium in bend tests. J. Nucl. Mater. 42, 317–324 (1972)
Kerr, M., Daymond, M.R., Holt, R.A., et al.: Strain evolution of zirconium hydride embedded in a Zircaloy-2 matrix. J. Nucl. Mater. 380, 70–75 (2008)
Kerr, M., Daymond, M.R., Holt, R.A., et al.: Fracture of a minority phase at a stress concentration observed with synchrotron X-ray diffraction. Scripta Mater. 61, 939–942 (2009)
Kerr, M., Daymond, M.R., Holt, R.A., et al.: Observation of growth of a precipitate at a stress concentration by synchrotron X-ray diffraction. Scripta Mater. 62, 341–344 (2010)
Lee W.K., Vesely, P.J.: Unpublished. Kinectrics Inc., Toronto. Ontario, Canada (2001)
Leitch, B.W., Puls, M.P.: Finite element calculations of the accommodation energy of a misfitting precipitate in an elastic-plastic matrix. Metall. Trans. A 23A, 797–806 (1992)
Louthan Jr., M.R.: Cleavage in hydrided Zircaloy-2. Trans. A. ASM 57, 1004–1008 (1964)
Marshall, R.P., Louthan Jr., M.R.: Tensile properties of Zircaloy with oriented hydrides. Trans. ASM 56, 693–700 (1963)
Pan, Z.L., Puls, M.P.: Internal friction peaks associated with the behaviour of hydrogen in Zr and Zr–2.5Nb. Mater. Sci. Eng. A 442, 109–113 (2006)
Puls, M.P.: The Influence of hydride size and matrix strength on fracture initiation at hydrides in zirconium alloys. Metall. Trans. A 19A, 1507–1522 (1988)
Puls, M.P.: Fracture initiation at hydrides in zirconium. Metall. Trans. A 22A, 2327–2337 (1991)
Puls, M.P., Shi, S.Q., Rabier, J.: Experimental studies of mechanical properties of solid zirconium hydrides. J. Nucl. Mater. 336, 73–80 (2005)
Rodgers, D.K.: Unpublished. Atomic Energy of Canada Ltd., Chalk River Laboratories, Chalk River, Ontario, Canada (1990)
Scarth, D.A., Smith, E.: Developments in flaw evaluation for CANDU reactor Zr–Nb pressure tubes. J. Press. Vess. Technol. 123, 41–48 (2001)
Scarth, D.A., Smith, E.: The effect of plasticity on process-zone predictions of DHC initiation at a flaw in CANDU reactor Zr–Nb pressure tubes. J. Press. Vessels Pip. 437, 19–30 (2002)
Scully, C.J.: Unpublished. AECL, Chalk River Laboratories, Chalk River, Ontario, Canada (1984)
Shek, G.K., Cui, J., Perovic, V.: Overload fracture of flaw tip hydrides in Zr–2.5Nb pressure tubes. J. ASTM International 2: Paper ID JAI12435 (2005)
Shi, S.Q., Puls, M.P.: Fracture of hydride precipitates in Zr–2.5Nb alloys. J. Nucl. Mater. 275, 312–317 (1999)
Simpson, L.A.: Criteria for fracture initiation at hydrides in zirconium-2.5 pct niobium. Metall. Trans. A 12A, 2113–2124 (1981)
Simpson, L.A., Cann, C.D.: Fracture toughness of zirconium hydride and its influence on the crack resistance of zirconium alloys. J. Nucl. Mater. 87, 303–316 (1979)
Simpson, L.A., Chow, C.K.: Effect of metallurgical variables and temperature on the fracture toughness of zirconium alloy pressure tubes. In: Adamson, R.B., Van Swam, L.F.P. (eds.) Zirconium in the Nuclear Industry: Seventh International Symposium. ASTM STP, vol. 939, pp. 579–595 (1987)
Steuwer, A., Santisteban, J.R., Preuss, M., et al.: Evidence of stress-induced hydrogen ordering in zirconium hydrides. Acta Mater. 57, 145–152 (2009)
Steuwer, A., Daniels, J.E., Peel, M.J.: In situ crack growth studies of hydrided Zircaloy-2 on a single-edge notched tensile specimen. Scripta Mater. 61, 431–433 (2009)
Veleva, M., Arsène, S., Record, M.-C., et al.: Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part II. Morphology of hydrides investigated at different magnifications and their interaction with the processes of plastic deformation. Metall. Trans. A 34A, 567–578 (2003)
Wallace, A.C., Shek, G.K., Lepik, O.E.: Effects of hydride morphology on Zr–2.5Nb fracture toughness. In: Van Swam, L.F.P., Eucken, C.M. (eds.) Zirconium in the Nuclear Industry: Eighth International Symposium. ASTM STP, vol. 1023, pp. 66–88 (1989)
Westlake, D.G.: Initiation and propagation of microcracks in crystals of zirconium-hydrogen alloys. Trans. ASM 56, 1–10 (1963)
Yunchang, F., Koss, D.A.: The influence of multiaxial states of stress on the hydrogen embrittlement of zirconium alloy sheet. Metall. Trans. A 16A, 675–681 (1985)
Xu, F., Holt, R.A., Daymond, M.R., et al.: Development of internal strains in textured Zircaloy-2 during uni-axial deformation. Mat. Sci. Eng. A 488, 172–185 (2008)
Xu, F., Holt, R.A., Daymond, M.R.: Evidence for basal <a>-slip in Zircaloy-2 at room temperature from polycrystalline modeling. J. Nucl. Mater. 373, 217–225 (2008)
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
Copyright information
© 2012 Springer-Verlag London
About this chapter
Cite this chapter
Puls, M.P. (2012). Fracture Strength of Embedded Hydride Precipitates in Zirconium and its Alloys. In: The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components. Engineering Materials. Springer, London. https://doi.org/10.1007/978-1-4471-4195-2_9
Download citation
DOI: https://doi.org/10.1007/978-1-4471-4195-2_9
Published:
Publisher Name: Springer, London
Print ISBN: 978-1-4471-4194-5
Online ISBN: 978-1-4471-4195-2
eBook Packages: EngineeringEngineering (R0)