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Bong Goo Kim, Joy L. Rempe, Darrell L. Knudson, Keith G. Condie, Bulent H. Sencer
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 417-428
Technical Paper | Materials for Nuclear Systems | dx.doi.org/10.13182/NT12-A14173
Articles are hosted by Taylor and Francis Online.
An instrumented creep testing capability is being developed for specimens irradiated in pressurized water reactor coolant conditions at the Advanced Test Reactor (ATR). A test rig has been developed such that samples will be subjected to stresses up to 350 MPa at temperatures up to 370°C in pile. Initial Idaho National Laboratory (INL) efforts to develop this creep testing capability for the ATR are summarized. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper reports efforts by the INL to evaluate a prototype test rig in an autoclave at INL's High Temperature Test Laboratory. Data from autoclave tests with Type 304 stainless steel and copper specimens are reported.
