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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.
Eberhard Schuster, Kurt A. Pflugrad
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 192-196
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34270
Articles are hosted by Taylor and Francis Online.
Metal waste from nuclear power plants is normally contaminated with beta and gamma emitters mainly due to corrosion product radionuclides. Metal waste originating from reprocessing and fuel fabrication plants is contaminated only with alpha emitters (uranium). So far, only radionuclides that can be measured by gamma spectrometry can be quantified. The behavior of alpha emitters is investigated using an artificially added radionuclide in melt experiments. During its 1984–1988 program on decommissioning of nuclear installations, the Commission of the European Communities concluded a 2-yr research contract with Siemens AG, UB Kraftwerk Union on the behavior of radionuclides that are difficult to measure in the melting of steel. Investigation of the radionuclides 55Fe, 63Ni, and 90Sr began with melt experiments on 55Fe (considered an epsilon emitter) at laboratory scale, which showed that this nuclide is probably as homogeneously distributed in the melt as 60Co; thus, 60Co can be used as an isotopic indicator for 55Fe. In another melt experiment, 241Am was artificially added to metal waste and melted, showing a decontamination factor of ∼100 even with a very small quantity added (4 × 10−7 g 241Am). As of mid-1988, four melt experiments, each with different melt parameters, have been carried out. The last experiment relates to the melting of carbon steel with metallic uranium additions; although this experiment is not yet completely evaluated, problems related to the direct alpha measuring technique may arise from the disturbance of the radiochemical equilibrium of the uranium decay chain in the melt process.