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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.
V. J. Corcoran, C. A. Campbell, P. B. Bothwell
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 727-732
Waste Management | doi.org/10.13182/FST92-A29834
Articles are hosted by Taylor and Francis Online.
Current UK strategy for decommissioning stainless steel plant used for tritium containment centres on heating/melting the bulk metal to effect release of dissolved gases. However, hydrogen isotope containment vessels used for approximately 20 years with mercury pumps and exposed to air and water impurities, exhibit tritium burdens greatly exceeding those predicted by simple gas solution in the parent metal. Investigation into the location of, and activity release from, the vessel material indicate the existence of two major tritium sinks:- (i) the bulk metal where in-depth contamination arises from diffusion/solution; and (ii) a highly active surface layer, responsible for holding the main tritium inventory. The relatively rapid release of tritium from the surface layer at room temperature, particularly under moist conditions demands that this latter activity must be removed before plant dismantling and heating/melting is effected. Against this requirement, laboratory work has been performed to evaluate methods of effectively decontaminating stainless steel plant items by gas purge and heat treatment and also to confirm theoretical diffusion/solution calculations as an acceptable baseline for estimating gas solution in the bulk metal. This work reports the effect of wet outgassing primary containments and the effect of heating/melting on tritium burdens in stainless steel.