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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.
W. Cyrus Proctor, J. Michael Doster
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 339-359
Technical Paper | Fission Reactors/Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A14167
Articles are hosted by Taylor and Francis Online.
Local space and energy impact densities of various types of loose parts have been generated within a representative steam generator inlet plenum. This work expands upon previous experimental research to identify important mechanisms that govern accumulated loose part damage to steam generator tube sheets. As a result, a computational model for estimating loose part impact damage, including damage to steam generator tube ends from multiple impacts, was previously created. Damage effects were determined to be local effects that depended only on single impacts and impact overlaps in a small region of interest. It was found that the damage could be directly related to local impact density on the steam generator tube sheet.In this work, three-dimensional flow fields were generated, first for a previously used 1:8 scale experimental inlet plenum and then for a 1:1 scale Westinghouse type D steam generator. Monte Carlo simulations were carried out as a function of coolant temperature, coolant inlet velocity, loose part type, shape, mass, density, initial starting location, and initial kinetic energy. No a priori knowledge was assumed for the initial starting location and initial kinetic energy of the parts. Comparisons were performed between previous scaled experimental results and scaled computational simulation results to assess the validity of predictions from the scaled simulation. Combined, both this work and previous work could allow for the assessment of impact damage rates on steam generator tube sheets via simulation.The most-energetic impacts are not localized to any particular region on the tube sheet. The general progression of the spatial distribution of all impact locations as a function of initial kinetic energy accurately depicts the progression for the highest-energy impacts. As the initial kinetic energy increases and as the starting location moves toward the inlet plenum, there is an increase in the number of higher-energy impacts. The higher-initial kinetic energy impacts lead to higher-energy first impacts on the tube sheet. Beyond the first impact, the energy distribution is invariant to initial kinetic energy and initial start location. The invariance seen in the energy distribution does not hold the same for the spatial distribution. The effects of the initial kinetic energy and initial start location ripple into the second and third impacts. Beyond the third impacts little to no change can be discerned and the invariance due to initial kinetic energy and initial start locations is valid. Ultimately, with these types of analyses, reactor facilities will be able to better judge whether a system necessarily needs to shut down due to safety concerns about loose parts damage before a scheduled outage.