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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.
T.F. Yang, R.J. LeClaire, E.S. Bobrov, L. Bromberg, D.R. Cohn, J.E.C. Williams
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 838-842
Magnet Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40137
Articles are hosted by Taylor and Francis Online.
A conceptual design for a demountable TF coil is presented. The work is being pursued as part of an ongoing study of the Resistive Magnet Commercial Tokamak Reactor (RCTR) at MIT. The RCTR is an attractive commercial tokamak option which utilizes resistive magnets characterized by low stresses, low current density and moderate dissipated power. The demountable coil design for RCTR presented here features a relatively simple configuration with a large cross-section available for current transfer in the joint. The concept allows for complete removal of the TF coil with the blanket/first wall in place. Analysis also indicates significant advantages for the overall RCTR concept due to the possibility of placement of the EF and OH coils within the TF bore. These advantages include reduced PF coil size, dissipated power and TF overturning.