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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.
M. Z. Hasan, T. Kunugi
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1030-1035
Blanket Technology | doi.org/10.13182/FST91-A29478
Articles are hosted by Taylor and Francis Online.
Convective heat transfer in the thermally developing region in a coolant channel of the first wall and limiter/divertor plates of a fusion reactor has been analyzed numerically. The surface heat flux on a coolant channel in these plasma facing components varies circumferentially. The flow is assumed MHD fully developed laminar in a circular tube with insulating wall and in the presence of a transverse magnetic field. Both the circumferential variation of the surface heat flux and the presence of a transverse magnetic field greatly affect the steady-state Nusselt number and thermal entry length. At the point where the magnetic field is normal to the tube wall, the steady-state Nusselt number can be increased as much as by a factor of 2 compared with 4.36 for non-MHD flow (parabolic velocity profile) and uniform surface heat flux. The nonuniformity of surface heat flux, on the other hand, can reduce the Nusselt number at the same location (also the point of maximum heat flux) to about 3.0. The transverse magnetic field can increase the thermal entry length by about 40% compared with that for non-MHD flow and uniform heat flux. The nonuniformity of surface heat flux and transverse magnetic field combined can increase the thermal entry length by a factor of 4.6. Neglect of this decrease in Nusselt number can result in an underestimation of the film temperature drop by 38% to 64%. The increase in the entry length would not affect the thermal-hydraulic designs of the first wall and divertor plate because, even with this increase, the entry length is short for liquid-metal coolants.