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ANS Student Conference 2025
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.
Kwang-Wook Kim, Keun-Young Lee, Eil-Hee Lee, Yeji Baek, Dong-Yong Chung, Jei-Kwon Moon
Nuclear Technology | Volume 193 | Number 2 | February 2016 | Pages 318-329
Technical Paper | doi.org/10.13182/NT15-23
Articles are hosted by Taylor and Francis Online.
This work studied a concept of prompt countermeasure to minimize the accumulation of radioactive wastewater generated in severe nuclear accidents like the Fukushima Daiichi accident. A sequential precipitation process for the removal of Cs, Sr, I, and residual nuclides of Co, Mn, Sb, and Ru was suggested as a way to embody this concept. The process was confirmed to be possible as an effective and rapid emergency treatment for radioactive wastewater using many experiments with non-radioactive and active nuclides. Cobalt ferrocyanide–impregnated chabazite zeolite, Ba-impregnated 4A zeolite, and Ag-impregnated 13X zeolite were chosen as adsorbents for Cs, Sr, and I in this work had very high selectivities and fast adsorption rates with decontamination factors (DFs) on the order of 102 to 103. The adsorbent powders were rapidly settled in solution within 5 to 10 min by adding a coagulant of ferric ions. The residual nuclides could be removed by coprecipitation using ferric ion and flocculation using anionic polyacrylamide with DFs of more than 100 within 10 min.
