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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.
Satoshi Sato, Yasushi Seki, Romano Plenteda, Takashi Inoue, Davide Valenza, Robert T. Santoro, Hiromasa Iida, Hideyuki Takatsu, Kohbun Yamada, Yoshihiro Ohara, Toshihisa Utsumi
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 1002-1007
Neutronics Experiments and Analysis (Poster Session) | doi.org/10.13182/FST98-A11963744
Articles are hosted by Taylor and Francis Online.
Shielding analyses of the ITER neutral beam injector (NBI) ports have been performed using three-dimensional Monte Carlo and two-dimensional discrete ordinates Sn methods. The biological dose rates inside the cryostat after reactor shutdown are expected to be lower than design target of 100 μSv/h for the current NBI reference design with ∼60 cm thick NBI port walls. It was also observed that the total nuclear heating in the toroidal field (TF) coils satisfies the design limit of 17 kW when the port wall is 40 cm thick. The Sn calculations, performed using a rectangular model of the NBI, overestimate the dose rates at the cryostat and nuclear heating in TF coils by factors of ten and two, respectively, compared to Monte Carlo results obtained using a more accurate representation of the NBI system.
