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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.
A.G. Heics, W.T. Shmayda, R. Matsugu, S.K. Sood, K. Kalyanam, G.M. Pien, S. Letzring
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1515-1520
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30627
Articles are hosted by Taylor and Francis Online.
The Omega Upgrade at the Laboratory for Laser Energetics will commence deuterium-tritium (DT) shots in 1995. Omega Upgrade utilizes a 350 nm, 30 kJ laser to energize DT filled targets contained within an evacuated target chamber (TC). Up to 10 DT shots per day are planned, 5 days a week, with each target containing 20 mCi of tritium. Cryopumps, used to achieve high vacuum in the TC and to collect unburnt gases following DT shots, are regenerated on a monthly basis. The Tritium Scrubber System (TSS) has been designed to capture tritium released from the cryopumps, vacuum pump exhaust streams, outgassing from internal surfaces, and in the event of target rupture. A large quantity of low activity gas needs to be processed by the system; the target chamber and diagnostic antechambers will be evacuated up to 8 and 2000 times each month, respectively. The TSS has been designed to interface with existing equipment at the facility. To permit the safe handling of tritium gas products and to comply with emission regulations, modifications are required to the facility to enable the capture of tritiated species from exhaust streams before being released to the atmosphere. The targeted annual tritium emission for the facility is less than 10 mCi. The TSS utilizes zirconium alloy hydride beds and molecular sieve beds to detritiate exhaust streams prior to stacking to satisfy this stringent emission target.