Published 1978 | Version v1
Report Restricted

Effects of multiple transients on fast reactor fuel pin cladding mechanical properties

Description

The effects of various TREAT and simulated transient events on subsequent burst strength of 20% cold worked AISI 316 irradiated fast reactor fuel pin cladding were evaluated. Cladding strength after transient exposure was compared to strength prior to transient exposure, using a HEDL correlation of failure temperatures with irradiation and test parameters. The simulated transients and post-transient strength tests were performed in the Fuel Cladding Transient Tester (FCTT), which was developed at HEDL to simulate cladding conditions during in-reactor transient events by pressurizing tubing specimens under transient heating conditions

Availability note (English)

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

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
HEDL-SA--1598-FP

Conference

Title
1978 winter meeting of American Nuclear Society.
Dates
12 - 17 Nov 1978.
Place
Washington, DC, USA.

Optional Information

Secondary number(s)
CONF-781105--97.