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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.
Holly R. Trellue, Richard J. Kapernick, D. V. Rao, J. Zhang, Jack D. Galloway
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 26-38
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT13-A15823
Articles are hosted by Taylor and Francis Online.
This paper describes a new reactor concept: the Salt-cooled Modular Innovative THorium HEavy water-moderated Reactor System (SMITHERS), which addresses the goals of (a) evolving deployment needs, (b) increasing overall fuel burnup, (c) reducing proliferation risk, and (d) providing high-efficiency power generation. The reactor is modular and thus scalable from a few to hundreds of megawatts(thermal). The concept further burns used fuel from light water reactors (LWRs) without aqueous separations, reducing costs and proliferation pathways relative to current reprocessing plants. The additional burning of LWR fuel reduces proliferation risk by reducing global inventories of plutonium from used fuel in a way that does not isolate weapons-useable material and that increases the amount of power produced per ton of mined uranium. Improved fuel utilization through the potential use of thorium provides cost benefits by increasing neutron economy and enabling operation at higher efficiencies. Neutron economy is increased by using the lower neutron energies associated with large quantities of heavy water moderation and/or thorium for innovative reactor control and constant long-term power generation (i.e., sustainability). Finally, the proposed reactor also generates high-temperature coolant discharge in the form of liquid salt without coolant pressurization for external process heat applications such as oil extraction. Salt offers significant improvement over existing coolants such as light water and heavy water, which require pressurization to operate at high temperatures, adding to the cost and complexity of reactor operation. SMITHERS designs discussed in this paper either burned a full core of used fuel, ThO2 with 1.2 wt% PuO2 or other fissile material, or a combination of the two.