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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.
R.A.H. Edwards
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1472-1477
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-A30620
Articles are hosted by Taylor and Francis Online.
Treatment of tritiated waste from fusion power reactors has received little attention. Wastes will need detritiation involving isotope swamping before disposal, recycling or exemption. Work on detritiation techniques should consider the isotopic dilution involved as well as decontamination factor, volume reduction and product homogeneity; for the cost of tritium recovery from the contaminated water (or hydrogen) produced is highest for tritium levels just above the release limits. Most important to the overall costs of tritiated waste disposal are release and declassification limits.