DEVELOPMENT OF MARTENSITIC STEELS FOR HIGH NEUTRON DAMAGE APPLICATIONS

Authors
Citation
Ds. Gelles, DEVELOPMENT OF MARTENSITIC STEELS FOR HIGH NEUTRON DAMAGE APPLICATIONS, Journal of nuclear materials, 239(1-3), 1996, pp. 99-106
Citations number
56
Categorie Soggetti
Nuclear Sciences & Tecnology","Mining & Mineral Processing","Material Science
ISSN journal
00223115
Volume
239
Issue
1-3
Year of publication
1996
Pages
99 - 106
Database
ISI
SICI code
0022-3115(1996)239:1-3<99:DOMSFH>2.0.ZU;2-A
Abstract
Martensitic stainless steels have been developed for both in-core appl ications in advanced liquid metal fast breeder reactors (LMFBR) and fo r first wall and structural materials applications for commercial fusi on reactors. It can now be shown that these steels can be expected to maintain properties to levels as high as 175 or 200 dpa, respectively. The 12Cr-1Mo-0.5W-0.2C alloy HT-9 has been extensively tested for LMF BR applications and shown to resist radiation damage, providing a cree p and swelling resistant alternative to austenitic steels. Degradation of fracture toughness and Charpy impact properties have been observed , but properties are sufficient to provide reliable service. In compar ison, alloys with lower chromium contents are found to decarburize in contact with liquid sodium and are therefore not recommended. Tungsten stabilized martensitic stainless steels have appropriate properties f or fusion applications. Radioactivity levels are benign less than 500 years after service, radiation damage resistance is excellent, includi ng impact properties, and swelling is modest. This report describes th e history of the development effort.