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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.
Yuji Nakamura, Masahiro Wakatani, Jean-Noel Leboeuf, B. A. Carreras, N. Dominguez, Jeff A. Holmes, V. E. Lynch, S. L. Painter, Luis Garcia
Fusion Science and Technology | Volume 19 | Number 2 | March 1991 | Pages 217-233
Technical Paper | Plasma Engineering | doi.org/10.13182/FST91-A29361
Articles are hosted by Taylor and Francis Online.
Confinement properties of l-2 torsatron/heliotron configurations with number of toroidal field periods, M, in the range of 10 to 14 are studied. This involves the calculation of zero-current and flux-conserving equilibria; stability against Mercier modes and low-n ideal modes, with n denoting the toroidal mode number; and orbit confinement of deeply trapped energetic particles. Optimization of both mag-netohydrodynamic (MHD) and transport properties is pursued under the condition of plasma aspect ratio A = R/a ≥ 7, with R denoting the major radius and a the average plasma radius. For configurations with M ≤ 12, an average MHD beta limit of 4 to 5% is possible. The addition of a quadrupole field improves the confinement of trapped particles at zero pressure, but particle losses increase with increasing beta. This loss is less severe if the vacuum magnetic axis is shifted slightly inward. A configuration with M = 10, a coil pitch parameter pc in the range 1.25 to 1.30, and an added quadrupole field satisfies the beta and energetic particle confinement requirements for the next generation of large torsatron/heliotron devices.
