ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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Nuclear Science and Engineering
Fusion Science and Technology
When deployments hit setbacks: Cautionary tales in Idaho and Alaska
Plans announced with fanfare sometimes falter in the face of competition or economics. Take NuScale Power’s plans for the Carbon Free Power Project in Idaho: The project was canceled in mid-November by NuScale and its first customer, Utah Associated Municipal Power Systems, after nearly a decade. The significance of that news depends on the observer. NuScale intends to focus on other sites and customers. Competitors may redouble efforts to tout their own designs and customer lists. Media found an opportunity to speculate about the future of advanced nuclear. And while many in the nuclear community believe the momentum in favor of new nuclear deployments is continuing—or even increasing as COP28 continues—others would caution against high hopes and point to the persistent obstacles of regulation, supply chain constraints, and financing costs.
Technical Session|Panel|Sponsored by RPD|Cosponsored by THD
Friday, December 3, 2021|8:00–9:45AM EST |Columbia 2
Gregory M. Core (INL)
Abdalla Abou-Jaoude (INL)
The Department of Energy (DOE) recently announced awardees to the Advanced Reactor Demonstration Program (ARDP). With teams assembled and activities commencing, this panel will showcase some of the design features of different reactors being planned for near-term demonstration. This includes concepts from both the reactor demonstration as well as risk reduction initiatives, notably Natrium, Xe-100, Hermes, and the Molten Chloride Reactor Experiment (MCRE). The panel will primarily focus on the technical design specifications of the reactor systems as they pertain to neutronics, material, and thermal hydraulics.
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