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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.
Y. Ueda, N. Ohno, S. Kajita, H. Kurishita, H. Iwakiri, K. Tokunaga, N. Yoshida
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 513-520
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | doi.org/10.13182/FST07-A1540
Articles are hosted by Taylor and Francis Online.
This paper reports Japanese activities on tungsten material development and the basic studies on plasma and tungsten interactions. Effects of helium ion irradiation on embrittlement and bubble formation of various tungsten materials have been intensively investigated in Japan. Details of the helium bubble formation mechanism, its effects on surface morphology ,and the impacts on dust formation are presented. Fine-grained and TiC fine-particles dispersed tungsten are being developed to increase the resistance of the material to degradation in the fusion reactor environment. Microstructures and specific features amenable to fusion environments are presented. The experimental results on repetitive heat pulses on surface roughening and cracking are shown. The repetitive heat pulse effects are very serious and further studies are needed. Important issues of tungsten material development for DEMO and commercial devices will be discussed.
