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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.
Matthew P. Simones, Sudarshan K. Loyalka
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 45-62
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-14
Articles are hosted by Taylor and Francis Online.
In high-temperature gas-cooled reactors (HTGRs), an improved understanding of the production of carbonaceous dust (e.g., by abrasion, corrosion, radiation damage, and gas-to-particle conversion) and the subsequent transport of the dust and associated sorbed fission products is needed. Diffusion charging and/or self-charging of the suspended dust particles (aerosol) is likely to occur, which affects how the aerosol evolves in time and ultimately deposits on surfaces. At present, nuclear reactor safety codes, such as MELCOR, do not account for these effects and there is currently no consensus on their importance, partly due to a lack of experimental data as well as tools for computations. Further experimentation and modeling of these effects are therefore needed to resolve these issues. We report on an experimental investigation of the coagulation of charged aerosols pertinent to HTGRs by measuring the evolution of size and charge distributions over time and comparing the experimental results with computations using the direct simulation Monte Carlo method. Measurements have been completed for both silver and carbon ultrafine aerosols using a tandem differential mobility analyzer and an open-flow coagulation chamber with a residence time of nearly 400 s. Results for both aerosols indicate that coagulation occurs faster than predicted by the simulations, at times differing by an order of magnitude. While the paper is focused on specific aerosols, it is of wider significance in that it provides the first such comparisons between data and simulations on charged aerosol coagulation.