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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.
Michael P. Manahan, Sr., Hassan S. Basha
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 389-398
Technical Paper | Material | doi.org/10.13182/NT91-A34533
Articles are hosted by Taylor and Francis Online.
The conventional approach to flux determination is to use high-purity dosimeters to characterize the neutron field. An alternative approach referred to as the material scrapings method is presented. Steel scrapings are cut from an in-service component and this material is used to measure the specific activity for various reactions. This approach enables the determination of the neutron flux and fluence incident on any component for which small chips of material can be safely obtained. The scrapings methodology was benchmarked by comparison with the results obtained using conventional dosimetry data from the San Onofre Nuclear Generation Station Unit 2. Pseudo fast fluxes (E 1.0 and 0.1 MeV) are cal culated by combining the surveillance capsule dosimetry measured activities with the corresponding effective cross sections. The effective cross sections for the reactions of interest are calculated using the analytically determined neutron spectrum at the surveillance capsule position. After the evaluation and testing of the surveillance capsule were completed, scrapings were taken from a broken Charpy specimen. The pseudo fluxes for the 54Fe(n,p)54Mn and 58Ni(n,p)58Co reactions were calculated using the same cross sections as those used for the capsule dosimetry analysis. The pseudo fluxes determined using the scrapings dosimetry are within 5% of the corresponding surveillance capsule pseudo fluxes.