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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
L. J. Bond, S. R. Doctor, J. W. Griffin, A. B. Hull, S. N. Malik
Nuclear Technology | Volume 173 | Number 1 | January 2011 | Pages 46-55
Technical Paper | NPIC&HMIT Special / Materials for Nuclear Systems | doi.org/10.13182/NT173-46
Articles are hosted by Taylor and Francis Online.
The U.S. Nuclear Regulatory Commission has undertaken a program to lay the groundwork for defining proactive actions to manage degradation of materials in light water reactors (LWRs). This proactive management of materials degradation (PMMD) program examines LWR component materials and the degradation phenomena that affect them. Of particular interest is how such phenomena can be monitored and data can be used to predict degradation and prevent component failure. Some forms of degradation, including some modes of stress corrosion cracking, are characterized by a long initiation time followed by a rapid growth phase, and monitoring such long-term degradation will require new nondestructive evaluation methods and measurement procedures. As reactor lifetimes are extended, degradation mechanisms previously considered too long-term to be of consequence (such as concrete and wiring insulation degradation) may become more important. This paper explains the basic principles of PMMD and its relationship to in-service inspection, condition-based maintenance, and advanced diagnostics and prognostics. It then reviews the phases for degradation development and technologies with potential for sensing and monitoring degradation in its early stages.