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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.
Yoshinari Oshimi, Mayu Ohki, Misato Nagano, Takuyo Yasumatsu, Masanori Hara, Satoshi Akamaru, Masato Nakayama, Miki Shoji
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 583-588
Technical Paper | doi.org/10.1080/15361055.2020.1729294
Articles are hosted by Taylor and Francis Online.
For low-level tritium measurements using a liquid scintillation counter, scintillation vial selection is important. The applicability of polyethylene (PE) vials was studied. Three types of vials were tested: (1) 100-mL perfluoroalkoxy alkane (PFA) fluorine resin vials, (2) 100-mL PE vials, and (3) 145-mL PE vials. Ultima Gold LLT was the reference liquid scintillator in this study. The background counts for these vials were found to be 2.5 counts per minute. Tritiated water of 1.5 Bq‧mL−1 was employed as an internal standard to determine the counting efficiency. The counting efficiencies for the 100-mL PFA, 100-mL PE, and 145-mL PE vials were estimated to be 17%, 16%, and 13%, respectively. The lower limits of detection of these vials for a counting time of 100 min were 1.45 Bq‧L−1 for 100-mL PFA vials, 1.54 Bq‧L−1 for 100-mL PE vials, and 1.47 Bq‧L−1 for 145-mL PE vials. Thus, these vials demonstrate similar performances for tritium measurements.