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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.
Y. Hatano, V. Kh. Alimov, A. V. Spitsyn, N. P. Bobyr, D. I. Cherkez, S. Abe, O. V. Ogorodnikova, N. S. Klimov, B. I. Khripunov, A. V. Golubeva, V. M. Chernov, M. Oyaidzu, T. Yamanishi, M. Matsuyama
Fusion Science and Technology | Volume 67 | Number 2 | March 2015 | Pages 361-364
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T30
Articles are hosted by Taylor and Francis Online.
The effects of displacement damage, plasma exposure and heat loads on T retention in reduced-activation ferritic/martensitic (RAFM) steels were investigated by exposing the steels to DT gas at 473 K. Despite enormous change in surface morphology, T retention in the heat-loaded specimen was comparable with that in the unloaded specimen. The exposure to plasma resulted in a drastic increase in T retention at the surface and/or sub surface. However, the T trapped at the surface/subsurface was easily removed by maintaining the specimens in air at ∼300 K. Formation of radiation-induced defects led to a significant increase in T retention, and T trapped in the defects was not removed at ∼300 K. These observations suggest that displacement damages have the largest effects on T retention at ∼473 K.