DEVELOPMENT OF ADVANCED AUSTENITIC STAINL ESS-STEEL FOR FAST-REACTOR CORE MATERIAL

Citation
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
Citations number
NO
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
00047120
Volume
36
Issue
5
Year of publication
1994
Pages
441 - 455
Database
ISI
SICI code
0004-7120(1994)36:5<441:DOAASE>2.0.ZU;2-3
Abstract
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.