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.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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
Fusion Science and Technology
Route readiness elements in a large-scale spent nuclear fuel transportation system
The scale and duration of a national campaign to transport spent nuclear fuel (SNF) from commercial nuclear power plants around the United States would be unprecedented. A meticulous level of planning that considers many elements is needed to inspire public confidence and support.
Technical Session|Sponsored by RPD
Wednesday, June 16, 2021|2:15–4:00PM EDT
Jason Hearne (Texas A&M Univ.)
Massimiliano Fratoni (Univ. of California Berkeley)
Pavel V. Tsvetkov
Susan Gallier (ANS)
This is a standing RPD session with papers on all reactor physics design, validation and operational experience topics of contemporary interest.
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Reactor Physics Analyses of the Big-BUSTER Testing Environment in TREAT
John D. Bess (INL), Nicolas E. Woolstenhulme (INL), Matthew R. Ramirez (INL), Wesley T. Smith (INL), Aaron S. Epiney (INL)
Review: Monte Carlo Neutronics Validation Studies of Burned Nuclear Material
Sean P. Martinson (Texas A&M Univ.), Sunil S. Chirayath (Texas A&M Univ.)
nTRACER Solutions to C5G7-TD Neutron Noise Simulation Benchmark
Junsu Kang (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Flexible Cross Section Generation in OpenMC with TOGA (Tool for Optimization and Group-Structure Analysis)
Miriam A. Kreher (MIT), Jack Galloway (LANL), Blake Wilkerson (ORNL), Joshua Richard (LANL)
Design and Heat Generation Rate Analysis of LEU-UAlx Dispersion Target Plates for Irradiation in the High Flux Isotope Reactor
Nolan Goth (ORNL), Trevor Howard (ORNL), Jorge Navarro (ORNL), Eliott Fountain (ORNL), Nesrin Cetiner (ORNL), Chris Bryan (ORNL)
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