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Thermal Hydraulics
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
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Latest News
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.
Kyu In Shin, Jae Sung Yoon, Dong Won Lee, Suk-Kwon Kim, Jin Hyung Gon, Eo Hwak Lee, Seungyon Cho
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 200-207
Technical Paper | doi.org/10.13182/FST13-752
Articles are hosted by Taylor and Francis Online.
Korea has developed a helium-cooled ceramic reflector (HCCR) test blanket module (TBM) for ITER, and Korean reduced activation ferritic martensitic (RAFM) steel, which is named ARAA (advanced reduced activation alloy), has also been developed for a structural material of the KO HCCR TBM. To evaluate the welding fabrication technology in the TBM, one case of TIG welding conditions was selected based on the previous work by Yoon et al. (2013), and a single pass with one side weld procedure through a thickness in TIG weld was carried out using ARAA, Batch 2 (F206). The microstructure was observed in the base, heat affected zone (HAZ), and weld region, and the micro-hardness was measured from the base to the weld region. In addition, a small punch (SP) test considering the base metal and HAZ region was carried out at room and high (550°C) temperatures. The empirical mechanical properties of the HAZ were estimated based on the correlation between the tensile and SP test in the base metal, and the fracture morphology was observed after the SP test.
