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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.
G. Pierini, R. Baratti, A.M. Polcaro, P.F. Ricci, A. Viola
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2121-2126
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24597
Articles are hosted by Taylor and Francis Online.
The extraction of tritium from the liquid alloy 17Li83Pb has been examined taking into consideration the equations related to the design of “droplet spray” and “bubble” extractors in order to verify which are the higher tritium recovery efficiencies which can be realized so as to minimize the permeation of tritium into the water of the cooling system. As far as the droplet spray unit is concerned, the tritium extraction efficiency has been correlated to tritium pressure in the extractor, to the droplet radius and to the residence time of the droplets in the extractor. For the tritium desorption from the alloy, flowing countercurrent to a helium stream in a bubble extractor, the axial dispersion in the liquid and gaseous phases and the effects of gas phase expansion caused by reduced hydrostatic head in the extractor are taken into account. From the results of this study, both the bubble and spray droplet extractors seem to be very appropriate units for tritium recovery from the alloy. Moreover, in order to reach high extraction efficiencies for reducing the tritium permeation to the water cooling system, the spray droplet extractor appears more suitable.
