Published February 1983 | Version v1
Report Restricted

Mechanical properties of irradiated fast breeder reactor cladding and ducts

Description

Austenitic stainless steels are being used for various core components in Liquid Metal Fast Breeder Reactors. Twenty percent cold worked Type 316 stainless steel is being used for both fuel pin cladding and ducts in the Fast Flux Test Facility. Safe and reliable operation of breeder reactors requires a characterization of the effects of fast neutron irradiation and environment on the mechanical properties of the cladding and duct material. Nearly 1400 tests have been conducted on unirradiated and irradiated cladding and duct samples under conditions relevant to reactor operational and transient events. Six different types of tests conducted on cladding and duct samples are described and the effects of irradiation on the properties are discussed

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE83015472.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
HEDL-SA--2728-FP

Conference

Title
7. international conference on structural mechanics in reactor technology.
Dates
22-26 Aug 1983.
Place
Chicago, IL (USA).

Optional Information

Secondary number(s)
CONF-830805--46.