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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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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.
Abdellatif M. Yacout, Won-Sik Yang, Gerard L. Hofman, Yuri Orechwa
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 61-72
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35275
Articles are hosted by Taylor and Francis Online.
Integral parameters of reactor fuel pins are usually measured after long periods of irradiation, where each period can extend over a number of irradiation cycles. Examples of these parameters include cladding diametral strain and parameters involved in the evaluation of fuel/cladding chemical interaction and fuel restructuring. Analysis of these parameters requires knowledge of calculated irradiation parameters, which can vary between irradiation cycles and within the cycles. Irradiation temperature is one such parameter. A calculated weighted average temperature that takes into account the fluctuations in temperature between irradiation cycles is introduced. The work discusses the justification for using this temperature and a methodology for its validation. The methodology is based on comparing calculated average temperatures with temperatures inferred from the postirradiation examination of restructured binary metallic fuel pins in the Experimental Breeder Reactor II. The analysis shows reasonable agreement between the two temperatures. The peak irradiation temperatures, which are usually used in the analysis, were out of the range of the temperatures inferred from the experimental observations, showing the importance of using the average temperature.
