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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.
E. T. Cheng
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 549-553
Technical Paper | Fusion Energy - Nonelectric Applications | doi.org/10.13182/FST03-A395
Articles are hosted by Taylor and Francis Online.
A fusion based actinide destruction system is advantageous because of higher actinide destruction efficiency and higher energy efficiency when compared to other destruction technologies. The unique neutron multiplication capability due to the n,2n reactions in blanket materials with 14 MeV D-T neutrons enhances further the performance efficiency.Investigation of a high performance fusion based actinide destruction system was conducted. A self-cooled, actinide-carrying molten salt blanket can be designed to operate at a high sub-criticality factor of 0.95-0.96, with less than 0.4 wt% actinide concentration dissolved in the molten salt. The corresponding blanket energy multiplication is 160. Lithium-6, which is required for tritium breeding, can be used as a variable to shape the neutron spectrum and control the criticality factor, and thus to maintain a constant fission thermal power output from the actinide destruction plant.Sub-criticality can be maintained in all cases of the actinide destruction plant, during normal operation and abnormal conditions.A fusion device projected from a tokamak experiment can produce 30 MW fusion power, with a plasma amplification factor of 2. It is considered adequate to drive the sub-critical molten salt blanket. The total thermal fission power is about 4000 MW, which is able to destroy 1.6 metric tons of actinides annually when operating at full power.