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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.
V. Ya. Goloborod'ko, V. V. Lutsenko, S. N. Reznik, V. A. Yavorskij
Fusion Science and Technology | Volume 27 | Number 3 | May 1995 | Pages 292-297
Technical Paper | Plasma Engineering | doi.org/10.13182/FST95-A30391
Articles are hosted by Taylor and Francis Online.
Three-dimensional Fokker-Planck simulation of collisional losses of mega-electron-volt fusion products in axisymmetric tokamaks with plasma currents I < 2 MA is carried out. The calculations take into account both loss due to radial diffusion and loss caused by pitch-angle scattering in the first-orbit loss region in velocity space. Collisional losses of deuterium-deuterium (D-D) fusion products in the energy range 0.5 ≤ ε/ε0 ≤ 1 (where ε0 is the birth energy) are found to be increased with plasma current and comparable to a first-orbit loss at I > 1.5 MA. The loss mechanism considered may be responsible for the observed experimentally delayed losses of D-D fusion products in the Tokamak Fusion Test Reactor (TFTR). The dependencies of collisional losses on plasma current, effective charge number of the plasma (Zeff), and aspect ratio are investigated. The distributions of escaped ions over pitch angles, energies, and poloidal angles are evaluated. The fraction of collisionally lost fast fusion products is shown to scale like (ν⊥/νs)0.6 or (here ν⊥ and νs are characteristic collision rates of pitch-angle scattering and slowing down, respectively). The approach used may be considered as an alternative to the approach based on Monte Carlo modeling of scattering and can serve as a validity check of the latter.