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Latest News
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.
Ion Cristescu, A. Bükki-Deme, R. Carr, N. Gramlich, R. Groessle, C. Melzer, P. Schaefer, Stefan Welte
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 225-230
Technical Paper | doi.org/10.1080/15361055.2017.1288057
Articles are hosted by Taylor and Francis Online.
The design of ITER tritium processing systems will benefit from experimental data and process validation based on experimental facilities that are ITER scale relevant. Several rigs and experimental facilities have been enhanced and developed at the Tritium Laboratory Karlsruhe (TLK) in order to explore a wide range of envisaged scenarios of tritium plant systems, such as the Water Detritiation System (WDS), Isotope Separation System (ISS) and highly tritiated water processing. In the last few years, detailed experimental investigations and process modeling have been conducted in relation to the Combined Electrolysis Catalytic Exchange and Isotope Separation (CECE-ISS) systems which were focused on evaluation of the impact of deuterium build-up and accumulation in the CECE system. An enhanced configuration of the ITER WDS has been developed, that allows mitigation of the effects due to deuterium accumulation and reduction of the tritium inventory within the electrolysis system. In addition, the benefits concerning the interface between the WDS and ISS are presented. Significant efforts have been made to enhance the simulation tool TRIMO++ that was calibrated against the experimental results collected from the experimental rigs. The new features of the simulation tools are introduced as well.
The main references of a new method aiming to mitigate the tritium permeation from the tritium processes streams into the non-contaminated streams such as steam generators are introduced. The reference configuration of first phase of the experimental rigs and the preliminary experimental activities are presented as well.