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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.
Yasushi Nomura, Hiroshi Okuno
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 142-152
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT95-A35074
Articles are hosted by Taylor and Francis Online.
For handling of nuclear fuel during reprocessing or for design of spent-fuel storage and transportation, one needs to know the scale of maximum credible criticality accidents, i.e., the total fission number so as to know the radiological exposure of working personnel as well as the risk to the public in the event of an accident. Some simplified evaluation models for conservatively predicting the number of total fissions during an accident are derived theoretically using the one-point adiabatic reactivity balance model for the homogeneous and heterogeneous systems, respectively, which are frequently seen in nuclear fuel facilities. These simplified evaluation models are subsequently validated with the transient experiment data and actual accident data published to date from the world nuclear community. Some conventionally used simplified evaluation models of this kind are quoted and compared with the results to show the convenience of the current models, having almost no restrictions in the application for any kind of nuclear fuel, material composition, geometry, and dimension, and thus, ensuring adequate margins for predicting the total fission number at the time of a critsssicality accident.
