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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.
August W. Cronenberg, Sidney Langer
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 234-242
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27651
Articles are hosted by Taylor and Francis Online.
Data from the Three Mile Island Unit 2 (TMI-2) accident have shown that only small amounts of iodine and cesium escaped the plant, on the order of tens of curies. To assess the chemical and physical processes responsible for such a limited release, a detailed investigation of iodine and cesium chemical and transport behavior during the core degradation phase of the TMI-2 accident was initiated. Analyses indicate elemental iodine and cesium release from fuel, which subsequently reacts with the high-temperature steam/ hydrogen effluent to produce the gaseous species Csl and CsOH. Partial condensation and chemisorption of CsOH in the upper reactor plenum and on hot-leg piping is also predicted, where loss of the CsOH molecule from a mixture of H2O, Csl, CsOH, and HI gases in chemical equilibrium can result in destabilization of the Csl molecule to replace CsOH, forming HI in the process. Likewise, Csl reaction with borated water is predicted to have resulted in partial conversion of Csl to cesium borate and HI. A combination of Csl, HI, and CsOH is therefore assessed to be the principal form of iodine and cesium transport leaving the reactor vessel during core degradation. These species were subsequently dissolved in water, resulting in large-scale retention of fission product iodine and cesium.