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- [11] INDENTATION CREEP OF ZIRCALOY-2 WELDS OF NUCLEAR-FUEL PINSJOURNAL OF NUCLEAR MATERIALS, 1993, 207 : 345 - 349KUTTY, TRGGANGULY, C
- [12] ULTRASONIC INSPECTION OF SOUNDNESS AND PENETRATION OF CORNER WELDS FOR CASINGS IN ZIRCALOY-2REVUE DE METALLURGIE-CAHIERS D INFORMATIONS TECHNIQUES, 1968, 65 (11): : 781 - &BITRAN, MLAURENTA.GSCHEIDEC.M
- [13] EFFECT OF IRRADIATION ON STRAIN AGEING IN ANNEALED ZIRCALOY-2JOURNAL OF NUCLEAR MATERIALS, 1968, 27 (01) : 108 - &VEEVERS, KROTSEY, WB
- [14] STUDY OF GROWTH OF OXIDE ON ZIRCONIUM AND ZIRCALOY-2JOURNAL OF NUCLEAR MATERIALS, 1971, 38 (03) : 329 - &DAVID, GGESCHIER, RROY, C
- [15] Heat capacity of hydrogenated Zircaloy-2 and high Fe ZircaloyJOURNAL OF NUCLEAR MATERIALS, 2003, 323 (01) : 101 - 107Une, KIshimoto, S
- [16] FRACTURE-MECHANICS ANALYSIS ON STRESS-CORROSION CRACK-GROWTH IN ZIRCALOY-2JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1984, 26 (12): : 1072 - 1082NISHIMURA, SSHIMADA, SNAGAI, MAMANO, KYAGAWA, G
- [17] Dissolution and precipitation behavior of hydrides in Zircaloy-2 and high Fe ZircaloyJOURNAL OF NUCLEAR MATERIALS, 2003, 322 (01) : 66 - 72Une, KIshimoto, S
- [18] PLATING ON ZIRCALOY-2JOURNAL OF THE LESS-COMMON METALS, 1981, 79 (02): : 261 - 270DINI, JWJOHNSON, HRJONES, A
- [20] Strain evolution of zirconium hydride embedded in a Zircaloy-2 matrixJOURNAL OF NUCLEAR MATERIALS, 2008, 380 (1-3) : 70 - 75Kerr, M.Daymond, M. R.Holt, R. A.Almer, J. D.