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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.
Giuseppe Modolo, Reinhard Odoj
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 80-86
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35337
Articles are hosted by Taylor and Francis Online.
According to the current state of the art in reprocessing technology, the 129I contained in spent fuel elements can be completely transferred to the dissolver off-gas and efficiently adsorbed on AgNO3-impregnated silica (AC 6120). For future transmutation, the 129I should again be separated selectively and as completely as possible (>99%) from the AC 6120 adsorption matrix. Experimental studies show that a quantitative recovery of the iodine is possible by wet chemical and thermal processes. Extraction experiments using iodine-loaded AC 6120 with sodium sulfide solution provide recovery rates of 99 ± 1%. Reduction with hydrogen at 500°C, in which gaseous HI was liberated, provided recovery rates of >99%. After the separation of iodine, the reduced AC 6120 can be used again as an adsorbent for molecular iodine.
