Iodine stress corrosion cracking of Zircaloy reactor cladding: iodine chemistry (a review)
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
Show source-provided references
1. B. Cox, B.A. Surette, J.C. Wood, in: Proceedings of the Conference on Environmental Degradation of Engineering Materials by Aggressive Environments, Blacksburg, VA, 1981, p. 293
2. Cox · J. Nucl. Mater. · 1990 · 170 · 110.1016/0022-3115(90)90321-D ↗
3. Cox · J. Nucl. Mater. · 1990 · 172 · 24910.1016/0022-3115(90)90282-R ↗
4. R.B. Adamson, B.C. Cheng, R.M. Kruger, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Monterey, USA, Am. Nucl. Soc., LaGrange Park, IL 60525, 1991
5. Videm · Ann. of Nucl. Energy · 1976 · 3 · 30510.1016/0306-4549(76)90057-8 ↗
6. K. Videm, L. Lunde, in: T.P. Papa-Zoglon (Ed.), Zirconium in the Nuclear Industry, Fourth Conference, ASTM STP 681, American Society for Testing and Materials, USA, 1979, p. 23410.1520/STP36671S ↗
7. K. Videm, L. Lunde, Topical Meeting on Water Reactor Fuel Performance, Proc. Amer. Nucl. Soc., St. Charles, IL, USA, 1977, p. 274
8. R.F. Mattas, F.L. Yaggee, L.A. Neimark, in: D.G. Franklin (Ed.), Zirconium in the Nuclear Industry, Fifth Conference, ASTM STP 754, American Society for Testing and Materials, 1982, p. 15810.1520/STP37053S ↗
9. M. Gartner, J.C. LaVake, Power ramp testing and non- destructive post-irradiation examinations of high burnup PWR fuel rods, Proceedings of the IAEA Meeting on Pellet-Cladding Interaction in Water Reactor Fuel, Seattle, 1983
10. M. Peehs, E. Steinberg, H. Stehle, in: Proceedings of the IAEA Meeting on Pellet-Cladding Interaction in Water Reactors, Risø, Denmark, 1980, p. 169, see also Ref. [81]
11. H. Knaab, M. Gartner, F. Sontheimer, Proceedings of the IAEA Meeting on Pellet-Cladding Interaction and Load-following Behaviour of Water Reactor Fuel, Lyon, 1987
12. N. Fuhrman, Evaluation of Fuel Performance in Main Yankee Core I – Task C, EPRI NP-218, EPRI, Palo Alto, CA, 197610.2172/7209794 ↗
13. J.H. Davies, H.S. Rosenbaum, J.S. Armijo, E. Rosicky, E.L. Esch, S.B. Wisner, Proceedings of the ANS Topical Meeting on Water Reactor Fuel Performance, ANS, St. Charles, IL, 1977, p. 230
14. Kleykamp · J. Nucl. Mater. · 1985 · 131 · 22110.1016/0022-3115(85)90460-X ↗
15. C. Lysell, D. Schrire, Proceedings of the IAEA Technical Committee Meeting on Fuel Performance at High Burnup for Water Reactors, Studsvik, Nyköping, June 5–8, 1990
16. D. Cubicciotti, R.L. Jones, B.C. Syrett, in: D.G. Franklin (Ed.), Zirconium in the Nuclear Industry, Fifth Conference, ASTM STP 754, American Society for Testing and Materials, 1982, p. 14610.1520/STP37052S ↗
17. Konashi · J. Nucl. Mater. · 1983 · 116 · 8610.1016/0022-3115(83)90296-9 ↗
18. A. Tasooji, R.E. Einziger, A.K. Miller, in: D.G. Franklin, R.B. Adamson (Eds.), Zirconium in the Nuclear Industry, Sixth International Symposium, ASTM STP 824, American Society for Testing and Materials, 1984, p. 59510.1520/STP34497S ↗
19. B. van der Schaaf, Zirconium in Nuclear Applications, ASTM STP 551, American Society for Testing Materials, 1974, p. 47910.1520/STP32135S ↗
20. Garlick · J. Nucl. Mater. · 1971 · 41 · 27410.1016/0022-3115(71)90165-6 ↗
21. Kreyns · J. Nucl. Mater. · 1976 · 61 · 20310.1016/0022-3115(76)90084-2 ↗
22. Schuster · J. Nucl. Mater. · 1992 · 189 · 15710.1016/0022-3115(92)90528-S ↗
23. Smith · J. Nucl. Mater. · 1979 · 80 · 29110.1016/0022-3115(79)90192-2 ↗
24. S. Djurle, G. Lysell, H. Mogard, Fourth UN International Conference on Peaceful Uses of Atomic Energy, vol. 10, 1971, p. 289
25. F.L. Yaggee, R.F. Mattas, L.A. Neimark (EPRI NP- 1155 Project 1027 Interim Report, September 1979) Final Report NP-1557, EPRI, Palo Alto, CA, 1980
26. Haddad · J. Nucl. Mater. · 1986 · 138 · 8110.1016/0022-3115(86)90258-8 ↗
27. S. Lynch, Proceedings of the 19th Ann. conf. Int. Metallogr. Soc., Toronto, 1988
28. D.S. Tomalin, Localized ductility of irradiated Zircaloy-2, in Zirconium in the Nuclear Industry, ASTM STP 633, American Society for Testing Materials, 1977, p. 56810.1520/STP35591S ↗
29. Cubicciotti · J. Nucl. Mater. · 1978 · 78 · 210.1016/0022-3115(78)90498-1 ↗
30. B. Cox, J.C. Wood, Corrosion problems in energy conversion and generation, in: C.S. Tedmon Jr. (Ed.), The Electrochemical Society, 1974, p. 275
31. D.S. Tomalin, R.B. Adamson, R.P. Gangloff in: T.P. Papa-Zoglon (Ed.), Zirconium in the Nuclear Industry, Fourth Conference, ASTM STP 681, American Society for Testing and Materials, 1979, p. 12210.1520/STP36676S ↗
32. D. Lee, R.B. Adamson, Zirconium in the Nuclear Industry, ASTM STP 633, American Society for Testing and Materials, 1977, p. 38510.1520/STP35582S ↗
33. C.C. Busby, R.P. Tucker, J.E. McCauley, Report WAPD-TM-1149, Westinghouse Electric Corp., Pittsburg, PA, 1974
34. D. Cubicciotti, R.L. Jones, B.C. Syrett, EPRI-NP-1329, EPRI, Palo Alto, CA, 198010.1016/0022-3115(80)90145-2 ↗
35. H.W. Wilson, K.K. Yoon, D.L. Baty, Proceedings of the American Nuclear Society Topical Meeting on Light Water Reactor Fuel Performance, Portland, OR, 1979, p. 246
36. Gangloff · Corrosion · 1979 · 35 · 31610.5006/0010-9312-35.7.316 ↗
37. B. Cox, in: T.P. Papa-Zoglon (Ed.), Zirconium in the Nuclear Industry, Fourth Conference, ASTM STP 681, American Society for Testing and Materials, 1979, p. 306
38. R.P. Gangloff, L.F. Coffin, GEC Report 79-CRD-016, 1979
39. F.L. Yaggee, R.F. Mattas, L.A. Neimark, Final Report NP-1557, EPRI, Palo Alto, CA, 1980
40. Videm · J. Nucl. Mater. · 1979 · 87 · 25910.1016/0022-3115(79)90562-2 ↗
41. A. Miller, H. Ocken, Iodine-induced SCC of Zircaloy: use of laboratory data to predict in-reactor behaviour, Proceedings of the IAEA Meeting on Pellet-Cladding Interaction in Water Reactors, Risø, Denmark, 1980
42. K. Une, Threshold values characterising iodine-induced SCC of Zircaloys obtained in laboratory experiments, Proceedings of the IAEA Meeting on Pellet-Cladding Interaction in Water Reactors, Risø, Denmark, 1980
43. Galvele · J. Nucl. Mater. · 1996 · 229 · 13910.1016/0022-3115(95)00208-1 ↗
44. Galvele · Corros. Sci. · 1987 · 27 · 110.1016/0010-938X(87)90117-X ↗
45. Une · Res. Mechanica · 1984 · 12 · 161
46. L. Lunde, K. Videm, S. Aas, Stress corrosion testing of irradiated Zircaloy cladding and its relevance to PCI failure, Proceedings of the IAEA Meeting on Pellet Cladding Interaction in Water Reactors, Risø, Denmark, 1980
47. B. Cox, Stress corrosion cracking of Zircaloys in iodine containing environments: Zirconium in Nuclear Applications, ASTM STP 551, American Society for Testing and Materials, 1974, p. 41910.1520/STP32129S ↗
48. J.A.L. Robertson, Engrg. Inst. of Canada J. (Nov./Dec. 1972) 9; Atom. En. of Canada Ltd., Rept. AECL-4366, 1973
49. A. Garlick, Proceedings of the British Nuclear Energy Society Conference on Environmental Effects on Reactor Materials, London, 1971, paper 3, British Nuclear Energy Society, London
50. G. Ostberg, AB Atomenergi Rept. S406 (1969)
51. J.C. Wood, Trans. Amer. Nucl. Soc. 17 (1973) 197
52. A.B. Bain, J.C. Wood, C.E. Coleman, Proceedings of the British Nuclear Energy Society Conference on Fuel Element Performance, London, 1973, British Nuclear Energy Society, London
53. Garzarolli · Kerntechnik · 1978 · 20 · 27
54. Te-Lin Yau, in: R.H. Jones (Ed.), Stress-corrosion Cracking, ASM, Metals Park, OH, 1992, Ch. 11
55. K. Pettersson, L. Hallstadius, H. Bergqvist, A. Nylund, C. Wikstrom, in: Proceedings of the Fifth International Conference on Degradation of Materials in Nuclear Power Systems, (1991/2), NACE, Houston, TX, 1992, p. 156
56. Wood · J. Nucl. Mater. · 1973 · 45 · 10510.1016/0022-3115(72)90178-X ↗
57. B. Cox, Atom. En. of Canada Ltd., Rept. AECL-4589, 1973
58. R. Sejnoha, J.C. Wood, in: T.P. Papa-Zoglon (Ed.), Zirconium in the Nuclear Industry, Fourth Conference, ASTM STP 681, American Society for Testing and Materials 1979, p. 26110.1520/STP36685S ↗
59. Shimada · J. Nucl. Sci. Tech. · 1983 · 20 · 59310.3327/jnst.20.593 ↗
60. I. Schuster, C. Lemaignan, in: Proceedings of the Conference on Corrosion-Deformation Reactions, Fontainbleu, France, Editions Physique, 1992, p. 26310.1016/0022-3115(92)90528-S ↗
61. Y.H. Kang, W.S. Ryu, K.S. Rheem, S.H. Kim, in: Proceedings of the Conference 9205370 – Tech. Cttee. on Fuel Failure, Dimitrovgrad, Russia, 1993, p. 211; order no. DE-94601238 (from NTIS)
62. Goryachev · J. Nucl. Mater. · 1992 · 199 · 5010.1016/0022-3115(92)90439-R ↗
63. Bibilashvily · J. Nucl. Mater. · 1995 · 224 · 30710.1016/0022-3115(95)00114-X ↗
64. Pulham · J. Nucl. Mater. · 1995 · 218 · 14310.1016/0022-3115(94)00518-4 ↗
65. Pulham · J. Nucl. Mater. · 1995 · 223 · 27710.1016/0022-3115(95)00010-0 ↗
66. Kinetics of formation of solid iodides on zirconium10.1016/0022-5088(81)90176-4 ↗
67. Bouffioux · J. Nucl. Mater. · 1979 · 87 · 25110.1016/0022-3115(79)90561-0 ↗
68. Une · J. Nucl. Mater. · 1979 · 87 · 20710.1016/0022-3115(79)90142-9 ↗
69. R.L. Fish, R.E. Einziger, Rept. HEDL-TME 81-3, Hanford Engrg. Devel. Lab., Richland, WA, 1981
70. J.S. Tulenko, H.W. Wilson, M.H. Montgomery, Proceedings of the American Nuclear Society Topical Meeting on Light Water Reactor Fuel Performance, Portland, OR, 1979, p. 49
71. Hofmann · J. Nucl. Mater. · 1982 · 107 · 29710.1016/0022-3115(82)90429-9 ↗
72. Busby · J. Nucl. Mater. · 1975 · 55 · 6410.1016/0022-3115(75)90137-3 ↗
73. Dam · Corros. Sci. · 1995 · 37 · 160510.1016/0010-938X(95)00062-O ↗
74. Saldanha · Mater. Perform. · 1995 · 35 · 67
75. Williford · J. Nucl. Mater. Nucl. Eng. Design · 1984 · 78 · 2310.1016/0029-5493(84)90070-0 ↗
76. Williford · J. Nucl. Mater. · 1985 · 132 · 5210.1016/0022-3115(85)90393-9 ↗
77. Peehs · J. Nucl. Mater. · 1979 · 87 · 27410.1016/0022-3115(79)90564-6 ↗
78. O. Kubaschewski, C.B. Alcock, Metallurgical Themochemistry, 5th edn., Pergamon, Oxford, 1979
79. Lamoreaux · J. Electrochem. Soc. · 1981 · 128 · 45710.1149/1.2127438 ↗
80. Götzmann · J. Nucl. Mater. · 1982 · 107 · 18510.1016/0022-3115(82)90420-2 ↗
81. M. Peehs, H. Stehle, E. Steinberg, in: T.P. Papa-Zoglon (Ed.), Zirconium in the Nuclear Industry. Fourth Conference, ASTM STP 681, American Society for Testing and Materials, 1979, p. 24410.1520/STP36684S ↗
82. D. Cubicciotti, Proceedings of the IAEA Specialists Meeting on Internal Fuel Rod Chemistry, Erlangen, 1979, p. 24
83. K. Videm, Defect Formation and Fission Products Proceedings of the OECD Enlarged Halden Group Meeting, Sanderstolen, 1977
84. Adolphson · Inorg. Chem. · 1976 · 15 · 182010.1021/ic50162a017 ↗
85. Daake · Inorg. Chem. · 1977 · 16 · 202910.1021/ic50174a041 ↗
86. Chen · J. Nucl. Mater. · 1988 · 151 · 22510.1016/0022-3115(88)90016-5 ↗
87. Cox · Langmuir · 1987 · 3 · 86710.1021/la00078a002 ↗
88. Konashi · J. Nucl. Mater. · 1984 · 125 · 24410.1016/0022-3115(84)90550-6 ↗
89. Ball · J. Nucl. Mater. · 1989 · 167 · 19110.1016/0022-3115(89)90442-X ↗
90. W.G. Burns, E.H.F. Cordfunke, P.A.V. Johnson, P.E. Potter, G. Prins, M.H. Rand, Fuel Rod Internal Chemistry and Fission Products Behaviour, IAEA, Vienna, 1986, IWGFPT/25
91. Platzman · Intl. J. Radiat. Isotopes · 1961 · 10 · 11610.1016/0020-708X(61)90108-9 ↗
92. R.L. Jones, D. Cubicciotti, Stress Corrosion Cracking of Zircaloys, EPRI NP-717, 1978
93. Cubicciotti · J. Nucl. Mater. · 1978 · 78 · 9610.1016/0022-3115(78)90508-1 ↗
94. Bazin · Trans. Am. Nucl. Soc. · 1975 · 20 · 235
95. J.C. Wood, D.G. Hardy, A.S. Bain, Proceedings of the Topical Meeting on Light Water Reactor Fuel Performance, Portland, OR, American Nuclear Society, Hinsdale, IL, 1979
96. B.C. Syrett, D. Cubicciotti, R.L. Jones, Zirconium in the Nuclear Industry, ASTM STP 633, American Society for Testing and Materials, 1977, p. 28110.1520/STP35576S ↗
97. O'Hare · J. Chem. Thermodyn. · 1978 · 6 · 96
98. Cordfunke · J. Chem. Thermodyn. · 1976 · 8 · 24110.1016/0021-9614(76)90101-4 ↗
99. Osborne · J. Chem. Thermodyn. · 1976 · 8 · 36110.1016/0021-9614(76)90076-8 ↗
100. Besmann · Nucl. Technol. · 1978 · 40 · 29710.13182/NT78-A26727 ↗