Stress-Rupture Properties of Irradiated and Unirradiated Hastelloy N Tubes

作者: H. E. McCoy , J. R. Weir

DOI: 10.13182/NT68-A26335

关键词:

摘要: AbstractThe stress-rupture properties of two heats Hastelloy N tubing have been determined at 760°C in the irradiated and unirradiated conditions. Irradiation reduced rupture life strain but produced no detectable effects on creep rate. The irradiation are rationalized basis behavior helium which is formed metal as a result 10B(n,α)7 Li reaction with thermal neutrons.

参考文章(8)
W. R. Martin, J. R. Weir, POSTIRRADIATION CREEP AND STRESS RUPTURE OF HASTELLOY N. Nuclear Technology. ,vol. 3, pp. 167- 177 ,(1967) , 10.13182/NT67-A27871
W. R. Martin, J. R. Weir, Effect of Elevated-Temperature Irradiation on Hastelloy N Nuclear Technology. ,vol. 1, pp. 160- 167 ,(1965) , 10.13182/NT65-A20485
D. Hull, D. E. Rimmer, The growth of grain-boundary voids under stress Philosophical Magazine. ,vol. 4, pp. 673- 687 ,(1959) , 10.1080/14786435908243264
P. R. B. HIGGINS, A. C. ROBERTS, REDUCTION IN DUCTILITY OF AUSTENITIC STAINLESS STEEL AFTER IRRADIATION Nature. ,vol. 206, pp. 1249- 1250 ,(1965) , 10.1038/2061249B0
R.W Balluffi, L.L Seigle, Growth of voids in metals during diffusion and creep Acta Metallurgica. ,vol. 5, pp. 449- 454 ,(1957) , 10.1016/0001-6160(57)90063-9
J.Neill Greenwood, D.R Miller, J.W Suiter, Intergranular cavitation in stressed metals Acta Metallurgica. ,vol. 2, pp. 250- 258 ,(1954) , 10.1016/0001-6160(54)90166-2
Gunji Shinoda, Tadao Sano, Tadakazu Sakurai, Tadashi Kawasaki, Hisashi Izumi, Studies on Creep Rupture Strength and Changes of Microstructure of Austenitic Stainless Steels Journal of The Japan Institute of Metals. ,vol. 24, pp. 818- 822 ,(1960) , 10.2320/JINSTMET1952.24.12_818