Preirradiation microstructural development designed to minimize properties degradation during irradiation in austenitic alloys

作者: P.J. Maziasz , T.K. Roche

DOI: 10.1016/0022-3115(82)90697-3

关键词:

摘要: Abstract The first-generation Prime Candidate Alloy (PCA) for the austenitic stainless steel class of alloys application as a Magnetic Fusion Energy (MFE) first-wall material is 14 Cr-16 Ni-0.25 Ti modification type 316 steel. A key parameter performance wall lifetime. ability to resist swelling and embrittlement during irradiation important longer lifetimes. microstructure that evolves primarily responsible both responses, helium plays central role in this microstructural evolution. This paper indicates how preirradiation microstructures employ control MC precipitation dislocation density are designed produced fusion PCA. These expected enable better swelling, phase instability irradiation.

参考文章(5)
E. E. Bloom, F. W. Wiffen, P. J. Maziasz, J. O. Stiegler, Temperature and fluence limits for a type 316 stainless-steel controlled thermonuclear reactor first wall Nuclear Technology. ,vol. 31, pp. 115- 122 ,(1976) , 10.13182/NT76-A31703
D. N. Braski, J. M. Leitnaker, Homogenization of Ti-Hastelloy-N Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science. ,vol. 10, pp. 427- 432 ,(1979) , 10.1007/BF02697069
E. E. Bloom, J. M. Leitnaker, J. O. Stiegler, Effect of neutron irradiation on the microstructure and properties of titanium-stabilized type 316 stainless steels Nuclear Technology. ,vol. 31, pp. 232- 243 ,(1976) , 10.13182/NT76-A31685
J.A. Spitznagel, F.W. Wiffen, F.V. Nolfi, Microstructures developed in ‘simulated’ fusion irradiations Journal of Nuclear Materials. ,vol. 85-86, pp. 629- 646 ,(1979) , 10.1016/0022-3115(79)90332-5
K. Farrell, Experimental effects of helium on cavity formation during irradiation—a review Radiation Effects and Defects in Solids. ,vol. 53, pp. 175- 194 ,(1980) , 10.1080/00337578008207114