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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.
S. Chiocchio, G. Federici, G. Janeschitz, R. Tivey, C. Baxi, J. R. Haines, M. A. Ulrickson
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 628-633
Divertor Experiment and Technology | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40227
Articles are hosted by Taylor and Francis Online.
The ITER Divertor design is based on the idea of extinguishing the plasma flame in a gas target. According to this scheme a large part of the power entering the divertor region would be dissipated through atomic and molecular reactions. These processes must take place along the whole extension of the divertor throat, in older to limit the thermal loads and particle fluxes onto the target. Thus, the divertor channel walls have to be shaped in order to achieve an adequate heat removal capability and to allow an effective recirculation of the gas from the target to the upper part of the divertor region. This paper describes the main features of the Power Exhaust Structure of the ITER Divertor, which composes the side wall of the divertor channel. In the selected design, the side wall is formed by wing like plates (fins/vanes) twisted 45 degrees in the toroidal direction towards the incoming magnetic field lines. The shape and size of these vanes are determined by the requirement for providing a highly transparent wall, coupled with the need to minimize the thermal deflections and stresses of the structure induced by thermal and electromagnetic loads. The wings are made of copper and protected from the plasma by armor made from either Be or W. In this paper we present the basic features of the proposed design and report on the analyses carried out to assess the behavior of the vanes under the dominant loads. Also, the paper presents an assessment of the concept from the point of view of component fabrication, based on results of preliminary studies carried out to support the design of the ITER divertor.