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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.
Aaron T. Aoyama, Mohamad Dagher, Russell Feder, Michael Duco, Mahmoud Youssef
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 830-834
Computational Tools, Modeling & Validation | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12489
Articles are hosted by Taylor and Francis Online.
Neutron transport modeling of the ITER reactor structure including modeling the impact of potential neutron streaming along the divertor cassette requires a detailed 3-D CAD solid model of the ITER sector. An all-inclusive, full-scale CAD geometry model of a 40 degree section of the ITER reactor structure was developed for analytical use with the ATTILATM radiation transport code. The source geometry and model used was the reference 1/10th scale A-LITE 3 model provided by the ITER Project Office for radiation transport calculations. Model upscaling, examination, CAD-based cleanup and modifications were performed on each component using the commercial CAD software, SolidWorks. Based on the modified components a new full scale solid model of the ITER section including divertor cassettes was developed in order to ease the implementation of additional diagnostic components being designed by various parties.Geometry repair and modification operations were performed with the goal of obtaining a Parasolid model that would successfully import into and mesh in ATTILA. Many components were re-modeled in order to avoid faulty geometry entities that were identified after the scaling to full-size. This paper will discuss the development of this A-LITE CAD model, and its meshing in ATTILA.