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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.
S.Beloglazov, M.Nishikawa, T.Tanifuji
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1049-1053
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22744
Articles are hosted by Taylor and Francis Online.
In this paper we propose a model to explain tritium release from irradiated Li2ZrO3 sample made by Mitsubishi Atomic Power Industries Inc. (MAPI). The release curves were obtained by temperature programmed desorption (TPD) techniques in a series of experiments in Kyoto University Reactor (KUR) and in the JRR-4 reactor of the Japan Atomic Energy Research Institute (JAERI). In the model a number of mass transfer steps were taken into account. There were diffusion of tritium in the grain, adsorption and desorption of water on the surface of grains, two types of isotope exchange reactions, water formation reaction in addition of hydrogen to the purge gas. Tritium release curves for different purge gas compositions (N2, N2 + H2O) were calculated to compare with data obtained in the experiments. Apparent diffusivities of tritium in crystal grain of Li2ZrO3 were determined.
