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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.
Dong H. Nguyen
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 61-74
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34441
Articles are hosted by Taylor and Francis Online.
The design of the next generation of power reactors will emphasize passive safety and enhanced engineered systems. True passivity can be achieved by capitalizing on natural laws to restore reactor stability during an off-normal event. The most effective stabilizing mechanisms relying solely on natural laws— without human interference—are the feedback reactivities produced by a change in the reactor thermal state. During 1986 and 1987, an important research program was undertaken at the Fast Flux Test Facility (FFTF) to advance the understanding of feedback mechanisms and to investigate passive safety in liquid-metal reactors. The experimental program began with a series of static feedback reactivity measurements aimed at separating feedback components and ended with a demonstration of passive safety in a series of loss-of-flow-without-scram (LOFWOS) to natural circulation tests. Described here are (a) the fundamental experimental concepts used to unfold various feedback components, (b) the analysis of integral data used to construct feedback reactivity models, (c) the comparison of FFTF reactivities with mechanistic feedback models in the SASSYS/SAS4A code system, and (d) the pretest calculations for the LOFWOS test series, using the new FFTF feedback models.