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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.
C. E. Annese, E. Greenspan
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 958-962
Fusion Diagnostic and Neutronic Experiment and Analysis | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40278
Articles are hosted by Taylor and Francis Online.
The computer time saving attainable by solving the transport equation for the higher neutron energy groups and the diffusion equation for the lower energy groups was investigated for fusion reactor safety applications. For the ARIES-I design considered, it was found that coupled diffusion-transport solutions can provide the activation rates in all the zones excluding the shield to within 2.5 % and 5 % when the transition to the diffusion approximation is, respectively, at 1.4 MeV and 8.8 MeV. The corresponding saving in CPU time relative to an all-transport solution is 31 % and 43 %. For the low order transport approximation used, this CPU time is significantly shorter than that required by ONEDANT, with its built-in diffusion synthetic acceleration.
