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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
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.
Douglas W. Akers, Richard K. McCardell
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 264-272
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27653
Articles are hosted by Taylor and Francis Online.
The partitioning and release of fission products from fuel materials in the Three Mile Island Unit 2 (TMI-2) reactor pressure vessel (RPV) are summarized, and the chemistry that resulted in the observed behavior is discussed. As part of the TMI-2 core examination program, samples were examined from all regions within the RPV, from leadscrews in the upper plenum to previously molten material from the lower plenum of the RPV. The results of these examinations indicate significant variations in fission product behavior that were generally consistent with the volatility and chemical behavior of the expected fission product species. Low-volatility species (e.g., 144Ce) were retained almost entirely in the fuel material matrix, whereas unoxidized species such as 125Sb were found with the metallic structural materials. Most of the high-volatility species (137Cs and 129I) were released from the previously molten fuel; however, the releases were less than expected. These fission products were retained in previously molten fuel that contained concentrations of structural materials at the grain boundaries.