Irradiation performance of modified 316 stainless steel for Monju fuel

In situ observation of damage structure in ODS austenitic steel during electron irradiation

“…An advanced austenitic stainless steel, PNC316, was provided by JAEA [7], and the chemical composition is shown in Table 1. The ODS austenitic stainless steel (ODS-316) was fabricated by the MA process from argon gas-atomized PNC316 powder of ~150 μm diameter and 0.35 wt% Y 2 O 3 powder.…”

Irradiation Creep–Swelling Interaction in Modified 316 Stainless Steel up to 200 dpa

“…Based on the most extensive review by Garner 3) , Bo of austenitic stainless steels is typically in the range from 0.5 to 4 x10 -6 MPa -1 dpa -1 . It was also shown in the previous study that Bo ranges from 0.4 to 1.2 x10 -6 MPa -1 dpa -1 for modified 316 stainless steel 4) , which was developed for the Prototype Fast Breeder Reactor MONJU cladding in Japan Atomic Energy Agency (JAEA) and was designated PNC316 5,6) . This swelling independent term has been well interpreted in terms of the stress-induced preferential absorption (SIPA) mechanism under active investigations for many years.…”

Effect of neutron irradiation on the microstructure of modified SUS316 stainless steels

“…Because it was believed so far that the dissociation of acicular Fe 2 P during irradiation reduced the trapping effect on helium atoms and consequently swelling was induced [5,7].…”

“…A chemical composition of PNC316 stainless steel was Fe-16Cr-14Ni-2.5Mo-0.25P-0.004B -0.1Ti-0.1Nb in wt% and a compositional design concept of this material can be found elsewhere [5]. The chemical composition and heat treatment condition are shown in Table 1.…”