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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
François Sagot, Didier van Houtte, Katsumi Okayama, Joel Hourtoule, Inho Song
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 134-138
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12340
Articles are hosted by Taylor and Francis Online.
As the next step in the development of fusion energy, ITER has to be safe, reliable and available whenever needed to produce the experimental data as defined by the scientific program. To ensure the success of this mission, a Reliability, Availability, Maintainability and Inspectability (RAMI) analysis is being performed on the ITER plant systems to optimize the design and prepare both operation and maintenance over the ITER life. This analysis relies on a functional breakdown translated to Reliability Block Diagrams (RBDs) and on a Failure Modes, Effects and Criticality Analysis (FMECA) to provide reliability and availability calculations, to highlight the technical risks and to prioritize the ways to mitigate them in order to maximize the availability of the machine for plasma operation. Standardization is one way of addressing this concern in a cost-effective manner, as reducing the diversity of components allows keeping a reduced stock of interchangeable spares available on short notice and reducing the time to repair after a failure.This paper will present this approach as it is applied on the ITER power supplies systems: the Coil Power Supply and Distribution System (CPSDS) and the Steady-State Electrical Network (SSEN).