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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.
Philip L. Matheson, Richard A. Nebel, Grant W. Mason
Fusion Science and Technology | Volume 18 | Number 2 | September 1990 | Pages 257-272
Technical Paper | Divertor System | doi.org/10.13182/FST90-A29298
Articles are hosted by Taylor and Francis Online.
Magnetic divertors have been proven successful in minimizing plasma/wall interactions and in leading to high-confinement regimes in tokamaks. This suggests that similar benefits may occur in a reversed-field pinch (RFP) fitted with a divertor. Previous experiments using divertors in an RFP have used a poloidal field divertor configuration such as those used in tokamaks. This study investigates another approach, a toroidal field divertor (TFD). A simple model of a poloidally symmetric TFD is presented and used in a three-dimensional magnetohydrodynamic code to study the response of the plasma to the large poloidal m = 0 perturbations caused by the divertor coils. It is found that the topology of the RFP-TFD system is much more complex than had been expected. The three-dimensional DEBS code shows that the divertor will not hinder the formation of a reversed toroidal field in the plasma, although the dynamics of its formation is altered when toroidal effects are considered. The plasma develops flows and currents in the throat of the divertor in response to the vacuumlike divertor fields. These flows and currents tend to restore the force-free character of the plasma.