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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.
Fabrice Bentivoglio, Nicolas Tauveron
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 55-75
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4008
Articles are hosted by Taylor and Francis Online.
In the framework of Generation IV, the Commissariat à l'Energie Atomique studies different concepts of gas-cooled reactors (GCRs). The estimation of thermal-hydraulic performances in steady-state and in transient operations is of high importance for the designer of such systems. These evaluations require efficient and reliable simulation tools capable of modeling the whole reactor, including the core, the core vessel, the piping, the heat exchangers, and the turbomachinery. CATHARE2 is a thermal-hydraulic one-dimensional reference safety code developed and assessed for pressurized water reactors. It has been adapted to deal also with GCR applications. The assessment for these new applications requires cross comparisons with experimental representative data. Thus, CATHARE2 is validated against existing experimental data, in particular, the German power plant Oberhausen II data. Oberhausen II was a 50-MW(electric) direct-cycle helium turbine plant, operated by the German utility Energie Versorgung Oberhausen. This paper presents the plant, with a large emphasis on the helium power conversion unit, the modeling, and the comparison between experimental data and simulation results for both steady-state and transient cases. The agreement between the experimental data and the CATHARE results is quite satisfactory for the analyzed cases.