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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.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Jonathan G. Teague, Roberta N. Mulford
Nuclear Technology | Volume 206 | Number 8 | August 2020 | Pages 1195-1212
Technical Paper | dx.doi.org/10.1080/00295450.2019.1701345
Articles are hosted by Taylor and Francis Online.
Impact testing of general purpose heat sources (GPHSs) and their component GPHS clads is done to benchmark extensive safety calculations quantifying launch safety. Impact testing is done in the Isotope Fuels Impact Tester (IFIT), a large-bore gas gun at Los Alamos National Laboratory. Efforts to conduct an impact test at the extreme low end of the temperature range for launch have highlighted uncertainties in determining the GPHS clad temperature during impact tests. In IFIT impact tests, the GPHS clad temperature is inferred from the temperature of the radiological confinement. Heating tests have been done in the IFIT to determine the fueled clad surface temperature as a function of the surface temperature of the tantalum radiological confinement can. Direct measurement of clad temperatures in the impact configuration are described and the effect of emissivity of the various components indicated. The analytical model used to predict clad temperatures is seen to work well at temperatures above 625°C. Appropriate values of emissivity for use in the model were measured in the experiment. Calculation of the experimental clad impact temperature using the ANSYS thermal transport model is necessary at clad temperatures below 625°C. ANSYS modeling indicates that the clad temperature in a recent low-temperature impact was outside the relevant range for launch safety modeling of GPHS clad behavior.