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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.
Daniel Magallon, Hermann Hohmann, Hubert Schins
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 79-90
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34652
Articles are hosted by Taylor and Francis Online.
Two experiments known as Tl and T2 are performed in the test section TERMOS of the FARO facility. Quantities of the order of 100 kg of molten pure UO2 ∼3000°C are poured into 130 kg of sodium at 400°C and 0.1 MPa contained in a 0.28-m-diam test tube over a height of 2.5 m. The tests show a melt delivery rate twice as high in T2 as in Tl. Because of the large scale of the experiment, the tests reveal new features concerning this type of interaction. Particularly, fuel/coolant interaction (FCI) occurs that induces stepwise penetration and dispersion of the melt, and a limitation of the melt quantity that could penetrate into the sodium. Sodium pressure peaks up to 6.0 MPa and pressurizations of the 0.150-m3 gas phase blanket up to 0.8 MPa are recorded. These FCIs are interpreted as vapor explosions in nearly saturated sodium. Quantities of 60 kg for Tl and 45 kg for T2 of UO2 fragments are collected in the debris catcher located at the bottom of the test tube. A debris bed structure resulting from this type of interaction is identified and characterized. Porosity is almost constant all over the bed height while permeability increases by a factor of 30 when going from the top to the bottom of the bed.
