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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.
Sudip S. Dosanjh
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 30-46
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34334
Articles are hosted by Taylor and Francis Online.
During severe light water reactor accidents like Three Mile Island Unit 2, the fuel rods can fragment and thus convert the reactor core into a large particle bed. The postdryout meltdown of such debris beds is examined. A two-dimensional model that considers the presence of oxidic (UO2 and ZrO2) as well as metallic (e.g., zirconium) constituents is developed. Key results are that (a) a dense metallic crust is created near the bottom of the bed as molten materials flow downward and freeze; (b) liquid accumulates above the blockage and if zirconium is present, the pool grows rapidly as molten zirconium dissolves both UO2 and ZrO2 particles; (c) if the melt wets the solid, a fraction of the melt flows radially outward under the action of capillary forces and freezes near the radial boundary; (d) in a non wetting system, all of the melt flows into the bottom of the bed; and (e) when zirconium and iron are in intimate contact and the zirconium metal atomic fraction is >0.33, these metals can liquefy and flow out of the bed very early in the meltdown sequence.