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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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ANS Student Conference 2025
April 3–5, 2025
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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.
Imtiaz K. Madni, Xiao-Dong Guo
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 203-212
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34690
Articles are hosted by Taylor and Francis Online.
The MELCOR computer code has been used to simulate the National Research Universal full-length high-temperature 2 (FLHT-2) test. Input data for the analysis were obtained from the FLHT-2 test Data Report and from SCDAP input. Results are presented for the transient liquid level in the test bundle, heat transfer to the bypass flow, cladding and shroud temperatures, and hydrogen generation. Comparisons are made with experimental data and with SCDAP calculations. Several sensitivity calculations with MELCOR, which explore the impact of varying user-input modeling and time-step control parameters on the predicted behavior, were also carried out.
