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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.
M. Sawan, L. El-Guebaly, P. Wilson
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 763-770
Technical Paper | Nuclear Analysis and Experiments | doi.org/10.13182/FST07-A1582
Articles are hosted by Taylor and Francis Online.
Detailed three-dimensional nuclear analyses have been carried out for the chamber of a power plant concept that utilizes the Z-Pinch driven inertial confinement technology with a target yield of 3 GJ and repetition rate of 0.1 Hz per chamber. The elliptical chamber concept was modeled with the double-layered Recyclable Transmission Lines (RTL). Thick liquid jets are utilized to breed tritium, absorb energy, and shield the chamber wall. Two liquid breeder options were considered; the molten salt Flibe and the LiPb eutectic (Li17Pb83). The chamber wall is made of the low activation ferritic steel alloy F82H. While both breeders have the potential for achieving tritium self-sufficiency, the thermal power is ~6.5% higher with LiPb. However, a 55% thicker jet zone is required with LiPb to provide adequate chamber wall shielding. A thicker chamber wall is required with LiPb to reduce the nuclear energy leakage below 1%. The chamber wall does not need replacement except for the top part around the jet nozzles. Helium production in the chamber wall protected by LiPb is much lower than that with Flibe. Rewelding is possible only in the lower part of chamber wall below the pool.