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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.
Yuichiro Asano, Noriko Asanuma, Toshihiko Ito, Makoto Kataoka, Shinya Fujino, Tomoo Yamamura, Wataru Sugiyama, Hiroshi Tomiyasu, Kunihiko Mizumachi, Yasuhisa Ikeda, Yukio Wada, Masami Asou
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 198-210
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35411
Articles are hosted by Taylor and Francis Online.
A new reprocessing system for spent nuclear fuels based on a precipitation method is proposed to recover uranium and transuranium elements from spent nuclear fuels in high ratios and to achieve extreme safety without any potential dangers. Experiments were carried out for a simulated fuel solution containing uranium and 17 major elements. The main reprocessing processes are as follows: (a) dissolution of U02 fuel under mild conditions; (b) neutralization of the dissolved fuel solution with Na2C03-NaHC03 mixed solutions, followed by the separation of precipitated fission products by centrifugation; (c) separation of cesium by a precipitation method using a tetraphenylborate ion; and (d) recovery of uranium (U) as a precipitate of the hydrolyzed compound from an alkaline solution. As a result, 99.95% of the U was recovered with the least amount of fission products, i.e., 10-5 g or even less in the recovered 1 g of U with the only exceptions being zirconium and molybdenum.