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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.
Takeshi Itoh, Yuji Torikai, Satoshi Ueda, Masao Matsuyama, Katsuyoshi Tatenuma, Kuniaki Watanabe
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 741-745
Decontamination and Waste | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22685
Articles are hosted by Taylor and Francis Online.
With regard to tritiated contaminants, effective and simple dry decontamination method using ozone gas were proposed. By the treatment in ozone gas of 400 ppmv at 400 K, in the cases of stainless steel, the decontamination efficiencies of over 99 % were obtained for 1 hour, and the decontamination efficiencies of aluminum were 80–86 %. By the treatment of ozone gas, the quantity of the carbon atom on the surface and in inside layer were decreased, and the oxidation on the surface and in inside was proceeded, which may be assumed and expected that the recombination, release and diffusion to the surface of tritium are prevented by a rigid oxide layer generated.The ozone gas treatment is easy to use and apply in practice with a simple and safe operation. Furthermore, gas-phase decontamination technology has many advantages over conventional wet methods, in particular, its simple control processes and small secondary waste. The proposed decontamination technology has the sufficient ability and potential to simplify a decontamination operation and reduce the large volumes waste.