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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.
Takumi Hayashi et al.
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 836-840
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9014
Articles are hosted by Taylor and Francis Online.
In order to investigate the function of water molecule for tritium transport behavior on the water-metal boundary, a series of experiments of tritium permeation into humid atmosphere was performed through pure iron piping with different surfaces of oxide etc., which contained about 1 kPa of pure tritium gas at 423 K. Chemical forms of tritium permeated into water were monitored continuously under purging outer jacket by <1000ppm of water vapor in Ar. Observation of metal surfaces was also carried out by Secondary Electron Microscope (SEM) and X-Ray Diffraction (XRD) analysis. The results were compared with those permeated into pressurized liquid water at 423 K.The actual tritium permeation rate into Ar with <1000 ppm of water vapor was not clearly changed that into liquid water. In the vapor atmosphere, a magnetite layer did not grow on the surface clearly, and tritium permeation rate and chemical species (∼100% of HTO) through pure iron piping with mechanically polished surface were not changed drastically comparing with data with a magnetite surface. On the other hand, hydrogen gas (HT) fraction of tritium permeated into the outer jacket increased drastically in case of a gold plating surface.