Internal pressurization creep of Zr alloys for spent-fuel dry storage feasibility

JOM

Volumn 52, Issue 9, 2000, Pages 34-38

  Murty, K L ^a  

^a NORTH CAROLINA STATE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CREEP; DEGRADATION; EXTRAPOLATION; FUEL STORAGE; METALLOGRAPHIC MICROSTRUCTURE; PRESSURIZATION; SPENT FUELS; STRESSES;

INTERNAL PRESSURIZATION CREEP; SPENT-FUEL DRY STORAGE FEASIBILITY;

ZIRCONIUM ALLOYS;

EID: 0034266516     PISSN: 10474838     EISSN: None     Source Type: Journal    
DOI: 10.1007/s11837-000-0185-y     Document Type: Article

References (48)

1. M. Peehs and J. Fleisch, "LWR Spent Fuel Storage Behavior," J. Nucl. Mater., 137 (1986), pp. 190-202.
2. M. Peehs, G. Kaspar, and E. Steinberg, "Experimentally Based Spent Fuel Dry Storage Performance Criteria," 3rd International Spent Fuel Storage Techniques Symposium and Workshop, vol. 1, S-316-S-331, U.S. DOE-CONF-86041/UC-85(1986), pp. S-316-S-331.
3. C. Pescatore, M.G. Cowgill, and T.M. Sullivan, "Zircaloy Cladding Performance Under Spent Fuel Conditions," Progress Report May 1-October 31, 1989, BNL 52235 (Upton, NY: Brookhaven National Laboratory, 1989).
4. B.A. Chin and E.R. Gilbert, "Prediction of Maximum Allowable Temperature for Dry Storage of Zircaloy-Clad Spent Fuel in Inert Atmosphere," Nucl. Tech., 85 (1989), pp. 57-65.
5. M. Mayuzumi. and T. Onchi., "A Method to Evaluate the Maximum Allowable Temperature of Spent Fuel in Dry Storage During a Postulated Accident," Nucl. Tech., 93 (1991), pp. 382-388.
6. C. Pescatore and M.G. Cowgill, "Temperature Limit Determination for the Inert Dry Storage of Spent Nuclear Fuel," EPRI Report TR-103949 (May 1994).
7. K.L. Murty, "Stress Corrosion Cracking and Pellet Cladding Mechanical Interaction of Zircaloys - Application to LWRs," Proc. of 5th National Convention on Corrosion (New Delhi, India: November 1999).
8. E.A. Preble, and K.L. Murty, "Influence of Intermetallic Precipitates on Corrosion Behavior of Zirconium Alloys," Proc. Int. Conf. Corrosion (CORCON-97) (1997), pp. 609-614.
9. M.F. Ashby, "A First Report on Deformation Mechanism Maps," Acta Met., 20 (1972), pp. 887-894; see also, H.J. Frost and M.F. Ashby, Deformation Mechanism Maps (Tarrytown, NY: Pergamon Press, 1982).
10. M.F. Ashby, "A First Report on Deformation Mechanism Maps," Acta Met., 20 (1972), pp. 887-894; see also, H.J. Frost and M.F. Ashby, Deformation Mechanism Maps (Tarrytown, NY: Pergamon Press, 1982).
11. D.B. Knorr and M.R. Notis, "Deformation Mechanism Mapping of α-Zr and Zirclaloy-2," J. Nucl. Mat., 56 (1975), pp. 18-23.
12. R. Raj and M.F. Ashby, "Intergranular Fracture at Elevated Temperature," Acta Met., 23 (1975), pp. 653-667.
13. R.L. Keusseyan, C.P. Hu, and C.Y. Li, "Creep Damage in Zircaloy-4 at LWR Temperatures," J. Nucl. Mat., 80 (1979), pp. 390-392.
14. A. Wolfenden and K. Farrel, "On the Question of Void Formation in Neutron Irradiated Zirconium," Scripta Met., 6 (1972), pp. 127-129.
15. M.H. Yoo, "Suppression of Void Formation in Zirconium," Zirconium in Nuclear Applications, ASTM STP 551 (Philadelphia, PA: ASTM, 1974), pp. 292-307.
16. M. Mayuzumi and T. Onchi., "Creep Deformation and Rupture Properties of Unirradiated Zircaloy-4 Nuclear Fuel Cladding Tube at Temperatures of 727 to 857 K," J. Nucl. Mater., 175 (1990), pp. 135-142.
17. R.E. Einziger et al., "High Temperature Post-Irradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods under Dry Storage Conditions," Nucl. Tech., 57 (1982), pp. 65-80.
18. R.E. Einziger and R. Kohli, "Low-Temperature Rupture Behavior of Zircaloy-Clad Pressurized Water Reactor Spent Fuel Rods under Dry Storage Conditions," Nucl. Tech., 67 (1984), pp. 107-123.
19. A.K. Miller et al., Estimates of Zircaloy Integrity During Dry Storage of Spent Nuclear Fuel, EPRI Report NP-6387 (Palo Alto, CA: EPRI, 1989).
20. Y. Zhou, "Burst Properties of Zirconium Alloys: Application to Dry Storage" (M.S. Thesis, North Carolina State University, 1999).
21. M. Mayuzumi and T. Onchi., "Creep Deformation of an Unirradiated Zircaloy-4 Nuclear Fuel Cladding Tube under Dry Storage Conditions," J. Nucl. Mater., 171 (1990), pp. 381-388.
22. T. Gray, S. Lewis, and A. Presson, "Gas Pressurization System Internal Pressure Gauge Design (GRYIPAS)," Senior Design Project Final Report (Raleigh, NC: Department of Nuclear Engineering, North Carolina State University, May 2000).
23. M. Mayuzumi and T. Onchi., "The Applicability of the Strain-Hardening Rule to Creep Deformation of Zircaloy-4 Fuel Cladding Tube during Dry Storage Condition," J. Nucl. Mater., 178 (1991), pp. 73-79.
24. K.L. Murty, "Significance and Role of Deformation Micromechanisms in Life-Predictive Modeling of Aging Structures," Appl. Mech. Rev., 46 (5) (1993), pp. 194-200.
25. K.L. Murty, G.S. Clevinger, and T.P. Papazoglou, "Thermal Creep of Zircaloy-4 Cladding," paper C3/4(Paper presented at the 4th Int. Conf. Structural Mechanics in Reactor Technology (SMiRT-4), San Francisco, CA, 1977).
26. Y. Matsuo, "Thermal Creep of Zircaloy-4 Cladding under Internal Pressure," J. Nucl. Sci. Tech., 24 (2) (1987), pp. 111-119.
27. K.L. Murty, "Creep Studies for Life-Prediction in Water Reactors," JOM, 51 (10) (1999), pp. 32-39.
28. K.L. Murty, and S.G. McDonald, "Tensile, Creep and Relaxation Characteristics of Zircaloy Cladding a 385 C," paper C2/3 (Paper presented at the 6th Int. Conf. Structural Mechanics in Reactor Technology (SMiRT-6), Paris, 1981).
29. J.E. Bird, A.K. Mukherjee and J.E. Dorn, "Correlations Between High-Temperature Creep Behavior and Structure," Quantitative Relation Between Structure and Properties (Jerusalem: Israel University Press, 1969), pp. 255-452.
30. R.L. Coble, "A Model for Boundary-Diffusion Controlled Creep in Polycrystalline Materials," J. Appl. Phys., 34 (1963), pp. 1679-1682.
31. B.V. Tanikella and K.L. Murty, "Transitions in Biaxial Creep of Zircaloy-4 Tubing" (Paper presented at the 2nd Asia-Pacific Symp. Advances in Engineering Plasticity and its Applications (AEPA-2), Beijing, 1994).
32. K.L. Murty, J. Ravi, and Wiratmo, "Transitions in Creep Mechanisms and Creep Anisotropy in Zr-1Nb-1Sn-0.2Fe Sheet," Nucl. Eng. And Design, 156 (1995), pp. 359-371.
33. K.E. Amin, A.K. Mukherjee, and J.E. Dorn, "A Universal Law for High-Temperature Diffusion Controlled Transient Creep," J. Mech. Phys. Solids, 18 (1970), pp. 413-426.
34. K.L. Murty and K.K. Yoon, "Creep Transients in Zircaloy Cladding," Scripta Met., 13 (1979), pp. 299-302.
35. K.L. Murty and B.L. Adams, "Biaxial Creep of Textured Zircaloy I: Experimental and Phenomenological Descriptions," Mat. Sci. and Eng., 70 (1985), pp. 169-180.
36. K.L. Murty, F.A. Mohamed, and J.E. Dorn, "Viscous Glide, Dislocation Climb and Newtonian Viscous Creep Deformation Mechanisms of High Temperature Creep in Al3Mg," Acta Met., 20 (1972), pp. 1009-1018.; see also K.L. Murty, "Transitions in Deformation Mechanisms in Class-A Alloys - Historical Perspective and Recent Applications to Microelectronic Solder and Nuclear Core Materials," Proc. Seventh Int. Conf. Creep and Fracture of Engineering Materials and Structures: Mechanisms of High Temperature Deformation, ed. J.C. Earthman and F.A. Mohamed (Warrendale, PA: TMS 1997), pp. 69-78.
37. K.L. Murty, F.A. Mohamed, and J.E. Dorn, "Viscous Glide, Dislocation Climb and Newtonian Viscous Creep Deformation Mechanisms of High Temperature Creep in Al3Mg," Acta Met., 20 (1972), pp. 1009-1018.; see also K.L. Murty, "Transitions in Deformation Mechanisms in Class-A Alloys - Historical Perspective and Recent Applications to Microelectronic Solder and Nuclear Core Materials," Proc. Seventh Int. Conf. Creep and Fracture of Engineering Materials and Structures: Mechanisms of High Temperature Deformation, ed. J.C. Earthman and F.A. Mohamed (Warrendale, PA: TMS 1997), pp. 69-78.
38. O.D. Sherby and P.M. Burke, "Mechanical Behavior of Crystalline Solids at Elevated Temperature," Progr. Mat. Sci., 13 (1967), pp. 325-390.
39. K.L. Murty, "Applications of Crystallographic Textures of Zirconium Alloys in Nuclear Industry," Zirconium in the Nuclear Industry: Eighth International Conference, ASTM STP 1023 (Philadelphia, PA: ASTM, 1989), pp. 570-595.
40. K.L. Murty, "Biaxial Creep of Zircaloy Cladding," Trans. Ind. Inst. Metals, 39 (1986), pp. 357-368.
41. K.L. Murty, "Zircaloy Life Prediction and new Generation Zircaloys for LWRs," Trans. IIM, 50 (1997), pp. 533-562.
42. H. Stehle, E. Steinberg, and E. Tenckoff, "Mechanical Anisotropy and Microstructure of Zircaloy Canning Tubes," ASTM STP 633 (Philadelphia, PA: ASTM, 1977), p. 486.
43. W.L. Daugherty and K.L. Murty, "Application of Texture in Predicting Nuclear Fuel Cladding Creep," Nucl. Technology, 80 (1988), pp. 443-450.
44. J.C. Earthman et al., "Effect of Grain-Shape Anisotropy and Texture on Balanced-Biaxial Creep of Ti and Zr alloys," JOM, 46 (10) (1994), pp. 48-54.
45. K.L. Murty, A. Paradkar, and S. Nangalia, "Effect of Stress-Ratio on Biaxial Creep and Dislocation Microstructures in Recrystallized Ti3A12.5V Tubing," Deformation, Processing and Properties of Structural Materials, ed. E.M. Talef, C.K. Syn, and D.R. Lesuer (Warrendale, PA: TMS, 2000), pp. 169-179.
46. A.R. Causey et al., "In-Reactor Deformation of Zr-2.5wt%Nb Pressure Tubes," Influence of Radiation on Material Properties: 13th International Symposium (Part II), ASTM STP 956 (Philadelphia, PA: ASTM, 1987), pp. 54-68.
47. V. Fidleris, "The Irradiation Creep and Growth Phenomena," J. Nucl. Mat., 159 (1988), pp. 22-42.
48. M. Limback and T. Andersson, "A Model for Analysis of the Effect of Final Annealing on the In- and Out-Reactor Creep Behavior of Zircaloy Cladding," Zirconium in the Nuclear Industry: Eleventh Int. Symp., ASTM STP 1295 (1996), pp. 448-468.