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Title: Irradiation performance of modified type 316 stainless steel for Monju fuel

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6672083
; ; ;  [1]
  1. Power Reactor and Nuclear Fuels Development Corp., Ibaraki-ken (Japan)

Material development for prototype fast breeder reactor Monju application sought to improve the standard Type 316 stainless steel within the range of its specification. The main effort was devoted to improve creep rupture strength and swelling resistance. These improvements were essentially the control of minor elements such as phosphorus, boron, titanium, and niobium within a range of 0.1 wt%. Finally specified material has a typical composition of Fe-16 Cr-14 Ni-0.05 C-2.5 Mo-0.7 Si-0.025 P-0.004 B-0.1 Ti-0.1 Nb and is used in the 20% cold-worked (cw) condition. This material was designated as PNC316. Out-of-reactor creep rupture strength of the PNC316 was the highest among the austenitic stainless steels of this class, which is more than three times as much improvement in strength as the developmental cladding.

OSTI ID:
6672083
Report Number(s):
CONF-921102-; CODEN: TANSAO
Journal Information:
Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
Country of Publication:
United States
Language:
English