MECHANICAL-PROPERTIES OF AUSTENITIC STAINLESS-STEELS IRRADIATED AT 323 K IN THE JAPAN MATERIALS TESTING REACTOR

Citation
Y. Matsui et al., MECHANICAL-PROPERTIES OF AUSTENITIC STAINLESS-STEELS IRRADIATED AT 323 K IN THE JAPAN MATERIALS TESTING REACTOR, Journal of nuclear materials, 237, 1996, pp. 188-191
Citations number
9
Categorie Soggetti
Nuclear Sciences & Tecnology","Mining & Mineral Processing","Material Science
ISSN journal
00223115
Volume
237
Year of publication
1996
Part
A
Pages
188 - 191
Database
ISI
SICI code
0022-3115(1996)237:<188:MOASIA>2.0.ZU;2-G
Abstract
The austenitic stainless steels of type 304 and type 316 and the preci pitation hardened type 630 stainless steel were irradiated to doses ra nging from 5 x 10(24) to 1.2 x 10(26) n/m(2) at 323 K in the Japan Mat erials Testing reactor (JMTR). Tensile and fracture toughness tests ha ve been carried out at 293 K. Type 304 and 316 steels in the solution annealed condition hardened by irradiation to about 700 MPa. Fracture toughness values for these steels decreased with dose. Only a small ha rdening occurred after irradiation for cold worked type 304 and precip itation hardened type 630 steels. The effect of irradiation on the fra cture surfaces was small.