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Division Spotlight
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.
Meeting Spotlight
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
December 2023
Nuclear Technology
Fusion Science and Technology
November 2023
Latest News
New U.K. report: Young people want to know more about nuclear
Almost two-thirds of 14- to 18-year-olds in the United Kingdom would consider a career in nuclear if they knew more about it, according to a new report, Nuclear Energy: Young People’s Views on Nuclear Energy and Careers in the Nuclear Sector, from the British Science Association (BSA).
About the report: The report was conducted as part of the BSA’s Future Forum program and was funded by Urenco, an international supplier of uranium enrichment services and fuel cycle products, as part of its commitment to education and skills development.
The report centered around an initial survey of 1,000 14- to 18-year-olds in England, Scotland, and Wales, with two follow-up workshops that were attended by 39 young people, providing the opportunity for more detailed responses.
Elia Merzari, Haomin Yuan, Misun Min, Dillon Shaver, Ronald Rahaman, Patrick Shriwise, Paul Romano, Alberto Talamo, Yu-Hsiang Lan, Derek Gaston, Richard Martineau, Paul Fischer, Yassin Hassan
Nuclear Technology | Volume 207 | Number 7 | July 2021 | Pages 1118-1141
Technical Paper | doi.org/10.1080/00295450.2020.1824471
Articles are hosted by Taylor and Francis Online.
This paper demonstrates a multiphysics solver for pebble-bed reactors, in particular, for Berkeley’s pebble-bed -fluoride-salt-cooled high-temperature reactor (PB-FHR) (Mark I design). The FHR is a class of advanced nuclear reactors that combines the robust coated particle fuel form from high-temperature gas-cooled reactors, the direct reactor auxiliary cooling system passive decay removal of liquid-metal fast reactors, and the transparent, high-volumetric heat capacitance liquid-fluoride salt working fluids (e.g., FLiBe) from molten salt reactors. This fuel and coolant combination enables FHRs to operate in a high-temperature, low-pressure design space that has beneficial safety and economic implications. The PB-FHR relies on a pebble-bed approach, and pebble-bed reactors are, in a sense, the poster child for multiscale analysis.
Relying heavily on the MultiApp capability of the Multiphysics Object-Oriented Simulation Environment (MOOSE), we have developed Cardinal, a new platform for lower-length-scale simulation of pebble-bed cores. The lower-length-scale simulator comprises three physics: neutronics (OpenMC), thermal fluids (Nek5000/NekRS), and fuel performance (BISON). Cardinal tightly couples all three physics and leverages advances in MOOSE, such as the MultiApp system and the concept of MOOSE-wrapped applications. Moreover, Cardinal can utilize graphics processing units for accelerating solutions. In this paper, we discuss the development of Cardinal and the verification and validation and demonstration simulations.