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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.B. Antoniazzi, W.T. Shmayda
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1457-1462
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-A30617
Articles are hosted by Taylor and Francis Online.
The production of large volumes of low specific activity waste is a byproduct of working with tritium. Reliable, labour minimized techniques for assessing the tritium bound in the waste is essential for an effective waste management program. This work examines the use of tritium outgassing rates from waste as a means of determining the bound inventory. A simple and inexpensive technique has been developed which, when combined with a sampling methodology, leads to accurate measurements of tritium outgassing rates. These outgassing rates when used in conjuction with the appropriate database will yield the inventory bound in the waste. The results of this study support the viability of the proposed approach.
