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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.
Martin R. Williamson, Laurence F. Miller, Indraneel Sen
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 413-420
Technical Paper | Radiation Measurements and General Information | doi.org/10.13182/NT12-A13484
Articles are hosted by Taylor and Francis Online.
A methodology for simulating a neutron detector's pulse-height spectra (PHS) utilizing semiempirical equations for the light yield nonproportionality of organic scintillators is described. Using these simulations, suitable material synthesis techniques are established for optimizing the performance of neutron scintillators. A MATLAB program suite was developed to automate the process of generating the PHS by pairing these semiempirical equations with results generated using Monte Carlo radiation transport code (MCNPX) particle track (PTRAC) output files. This is accomplished by first calculating the energy deposited in a detector from each charged-particle reaction product generated from a neutron absorption event by postprocessing the MCNPX PTRAC output files. The energy deposited from each charged particle is then used in semiempirical light yield equations to determine the fluorescent light energy output by each charged particle. Finally, the individual contributions from each charged particle are recombined to accurately simulate the pulse generated from the neutron absorption event.
