Fatigue and crack growth behavior of V-Cr-Ti alloys

Journal of Nuclear Materials

Volumn 233-237, Issue PART 1, 1996, Pages 488-491

  Gieseke, B G ^a,b   Stevens, C O ^a   Grossbeck, M L ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b Div of Cincinnati Test Systems   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CRACK PROPAGATION; DEGRADATION; FATIGUE OF MATERIALS; FATIGUE TESTING; SERVICE LIFE; STRENGTH OF MATERIALS; THERMAL EFFECTS;

FATIGUE RESISTANCE;

VANADIUM ALLOYS;

EID: 0030259771     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(96)00236-X     Document Type: Article

References (9)

1. K.C. Liu, J. Nucl. Mater. 103-104 (1981) 913-918.
2. R.W. Swindeman, ASTM STP 459, Am. Soc. Test. Mater. (1969) 31-41.
3. G.E. Korth and R.E. Schmunk, ASTM STP 683, ed. J.A. Sprague and D. Krammer, Am. Soc. Test. Mater. (1979) 466-476.
4. A.L. Eustice and O.N. Carlson, Trans. ASME 221 (1961) 238.
5. C.E. Jaske and N.D. Frey, Rockwell International, Report No. ESG-DOE-13307.
6. B.A. Loomis, Fusion Reactor Mater. Semiannu. Prog. Rep. for Period Ending March 31, 1991, U.S. Department of Energy, DOE/ER-0313/10(1991) 145-155.
7. M.L. Grossbeck and K.C. Liu, Nucl. Technol. 58 (1982) 538-547.
8. W. van Witzenburg and H.J. de Bruyne, ASTM STP 1175, Am. Soc. Test. Mater. (1993) 1201.
9. L.F. Coffin, Met. Trans. 3 (1972) 1777.