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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.
A. N. Perevezentsev, A. C. Bell
Fusion Science and Technology | Volume 53 | Number 3 | April 2008 | Pages 816-829
Technical Paper | doi.org/10.13182/FST08-A1737
Articles are hosted by Taylor and Francis Online.
This paper presents results from the concept evaluation, experimental trials, and design of a water detritiation facility (WDF) for the JET fusion machine. The design is based on the combined electrolysis and catalytic exchange process and will allow construction of the plant and for its integration into the JET tritium plant in three stages.The first stage includes a liquid phase catalytic exchange column and electrolyzer to concentrate the water into a smaller amount of tritium-enriched water. There would then be three options for dealing with this water: processing off-site, conversion to solid intermediate-level waste for disposal, and further processing on-site for complete tritium recovery. The latter option will require the second stage of implementation to integrate the WDF with the isotope separation system of the tritium plant. The third stage might be desirable to reduce the amount of time that the existing isotope separation system would need to be involved in the recovery of tritium from the WDF.