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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.
Stanislav P. Simakov, Boris V. Devkin, Michael G. Kobozev, Ulrich von Möllendorff, Dimitriy Yu. Chuvilin
Fusion Science and Technology | Volume 36 | Number 2 | September 1999 | Pages 173-180
Technical Paper | doi.org/10.13182/FST99-A100
Articles are hosted by Taylor and Francis Online.
The results of a transmission experiment on a spherical nickel shell with a 7.5-cm-thick wall and a 14-MeV neutron point source at the center are reported. The neutron leakage spectrum from 14 MeV down to 100 keV was measured by the time-of-flight (TOF) method. Descriptions of the experimental arrangement, TOF spectrometer, measurements, and data-reduction procedures are given. The measured data are compared with results obtained in other laboratories. Three-dimensional Monte Carlo calculations with the MCNP code using the FENDL-1, EFF-2.4, and JENDL-FF nuclear data libraries were made. The FENDL-1 library predicted the neutron leakage from nickel more accurately than the other libraries.
