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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
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Albuquerque, NM|The University of New Mexico
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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.
D. Wootan, R. Omberg, A. Casella, N. Lahaye, B. Mcdowell (PNNL), W. Stokes (Columbia Basin Consulting Group)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 36-44
The accident scenarios that need to be analyzed within Chapter 15 of a safety analysis report may vary significantly between advanced reactors and the light water reactors that compose the current commercial fleet. In anticipation of identifying scenarios of concern and developing methods for their analysis, correlations may be made to calculations and tests performed in support of the liquid metal and molten salt reactors that have been operated previously within the US. In this paper, we discuss efforts made to compare Chapter 15 considerations for a proposed lead-bismuth cooled reactor to those developed previously for the Fast Flux Test Facility (FFTF) and the GE-Hitachi PRISM reactor. Comparisons were also made with Beyond Design Basis Accidents for FFTF.