S. Shikakura et al., DEVELOPMENT OF ADVANCED AUSTENITIC STAINL ESS-STEEL FOR FAST-REACTOR CORE MATERIAL, Nippon Genshiryoku Gakkaishi, 36(5), 1994, pp. 441-455
Advanced austenitic stainless steel beyond the standard composition re
gion of SUS316 stainless steel PNC1520 has been successfully developed
. Optimization of the steel leads to a composition of -20Ni-0.06C-2.5M
o-1.7Mn-0.25Ti-0.1Nb-0.028P-0.004B through the alloying design and fab
rication tests. An extensive series of evaluation tests including out-
of-pile. sodium environment, neutron irradiation and fission product c
orrosion has confirmed that PNC1520 is superior in high temperature st
rength and irradiation resistance to PNC316 as a core material for the
prototype reactor MONJU. PNC1520 is the best candidate material for t
he Demonstration reactor and will be tested on the whole core scale in
JOYO MK-M to obtain the proven data.