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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.
H. A. Boniface, N. V. Gnanapragasam, D. K. Ryland, S. Suppiah, A. Perevezentsev
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 241-245
Technical Paper | doi.org/10.1080/15361055.2017.1290970
Articles are hosted by Taylor and Francis Online.
The Water Detritiation System (WDS) designed for ITER is based on the combined electrolysis and catalytic exchange(CECE) process to ensure the emission of tritium to the environment is maintained below very strict limits. The CECE process is one of the processes for tritium removal that CNL (Canadian Nuclear Laboratories, formerly Atomic Energy of Canada Ltd.) has studied, developed and successfully demonstrated. In this work, CNL evaluated ITER’s design conditions of the exchange column and the electrolyser – the two key components of the CECE process (and the ITER WDS system) – to assess the effectiveness of tritium removal and investigate options to improve it. The evaluation was done using CNL’s CECE process simulation according to a protocol set out by ITER. Initially, calibration (benchmarking) of CNL’s hydrogen-water exchange column model was performed with a standard data set for a specified column to determine modeling parameters that resulted in a good match with the tritium concentration data. The model was then applied (with the same parameters) to the current WDS design. Some optimized conditions for the CECE process that could improve performance of the WDS to meet its design criteria were determined. The details of some of these assessments are presented here with particular attention to the WDS case where the feed water contains high levels of deuterium.