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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.
Hilbert Christensen
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 358-364
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3768
Articles are hosted by Taylor and Francis Online.
A previously developed radiolysis model has been used to simulate experiments from four laboratories. The source strengths in the experiments with UO2, doped with 238Pu, were 0.01, 0.1, and 1 Ci/g. The agreement was good with the experimental results of Stroes-Gascoyne et al. for their sample with 0.1 Ci/g. Their sample containing 0.01 Ci/g gave a factor-of-3-higher calculated corrosion rate compared with the experimental rate. In the experiments of Cobos et al. and of Kelm and Bohnert, using alpha-doped UO2, the calculated corrosion rates were somewhat lower than the experimental rates. However, recent experiments by Rondinella et al. using UO2 with 10% doped 233U gave considerably lower corrosion rates in good agreement with the model. The calculated corrosion rates for the same source strength were about the same for the experiments by Stroes-Gascoyne et al., Kelm and Bohnert, and Cobos et al. However, the experimental rates varied considerably. The agreement was not good with experiments using Pu(VI) dissolved in solution, in which case the calculated corrosion rate was ten times or more than ten times lower than the experimental rate. The reason for this disagreement could be a chemical effect of Pu(VI) in the solution.