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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.
Y. Ikeda, C. Konno, T. Nakamura, A. Kumar, M. A. Abdou
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1961-1966
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29629
Articles are hosted by Taylor and Francis Online.
An experiment of Induced radioactivity and decayheat has been conducted in the framework of JAERI/USDOE collaborative program on the fusion blanket neutronics. Sixteen different materials have been irradiated in two typical DT neutron fields simulating spectra at the first wall and blanket regions of a fusion reactor. Induced radioactivity production profiles for both short and long irradiation times were analyzed by detecting associated γ-ray energy spectra. Energy release rate in material was characterized on the basis of the γ-ray emission data measured as well as β-ray contribution estimated. In this experimental study, focuses were placed not only on providing benchmark data for verification of the calculation code and nuclear data, but also on a comparative study for providing a guide line for the material selection concerning the dose rate as well as the decayheat after shutdown in the near term DT fusion devices.
