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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.
Juris Tiliks, Gunta Kizane, Aigars Vitins, Elina Kolodinska, Elisa Rabaglino
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 245-249
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3872
Articles are hosted by Taylor and Francis Online.
The effects of temperature, magnetic field (MF), and ionizing radiation on the release of tritium from the Be pebbles irradiated in the BERYLLIUM experiment in 1994 in Petten, The Netherlands (irradiation neutron fluence 1.24 × 1025 m-2, irradiation temperature 780 K, and 3H content 7 appm) were investigated in this study. Simultaneous action of these factors corresponds to the real operating conditions of the blanket of a fusion reactor. The total amount of tritium in a separate pebble, the chemical forms of localized tritium (T0, T2, and T+), and the tritium distribution in the pebble volume were determined by a lyomethod (dissolution). Thermoannealing experiments were performed at a constant temperature of 1123 K for 2 h under the following conditions: separately both in MF (1.7 T) and under fast electron radiation (E = 5 MeV; P = 14 MGyh-1) as well as under the action of all three factors. Tritium in the Be pebbles is localized for the most part as T2 (85 to 94%). The abundances of T+ (4 to 5%) and T0 (5 to 10%) are little. The tritium distribution in a pebble is not uniform; most of the tritium is localized in the inner part of a pebble. An MF of 1.7 T decreases slightly the fractional release of tritium under the given conditions of thermoannealing (from 30 to 25%), the fast electron radiation increases it (from 30 to 40%), but the simultaneous action of the MF and radiation increases it (from 30 to 54%). The effects observed are explained that the MF and radiation affect the concentration of main diffusing particles T0 in a beryllium matrix.