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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.
Arup K. Maji, Bruce Letellier, Kyle W. Ross, Daseri V. Rao, Luke Bartlein
Nuclear Technology | Volume 146 | Number 3 | June 2004 | Pages 279-289
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3506
Articles are hosted by Taylor and Francis Online.
This paper presents a comparison between computational fluid dynamics (CFD) analysis and experiments in order to help pressurized water reactor (PWR) plants develop a methodology for estimating the amount of insulation debris that may transport to the sump screens of an emergency core cooling system (ECCS). This information is essential for the resolution of Generic Safety Issue-191 on the safety margins of the ECCS systems subsequent to debris accumulation and head loss at the screen.Tests were carried out on a simulated containment floor in the laboratory to determine the flow velocities in which different types of objects including insulation debris would move along the floor. CFD analyses were independently carried out to determine the flow velocities in the containment under different flow rates and break locations. It was shown that the flow regimes predicted by the CFD analyses compare well with the experimentally observed movement along the floor. Based on this observation the transport fraction of different types of insulation debris can be estimated specific to any PWR plant.