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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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February 2024
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Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Technical Session|Sponsored by RPD
Tuesday, November 17, 2020|12:00–2:10PM EST
Session Chair:
Pavel V. Tsvetkov
Session Organizer:
Alternate Chair:
Massimiliano Fratoni
Staff Producer:
Jay Bogardus (American Nuclear Society)
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Triangle-based Quasi-diffusion Nodal Method for Fast Reactor Analysis
Muhammad R. Oktavian (Purdue University), Yunlin Xu (Purdue University)
Paper
Burnup-dependent GPS Method with Leakage Correction and Spectral Weighting in Core Depletion Analysis
Haesun Jeong (Korea Atomic Energy Research Institute), Hwanyeal Yu (Korea Advanced Institute of Science and Technology), Yonghee Kim (Korea Advanced Institute of Science and Technology)
Initial Control Rod Depletion Development in MPACT
Aaron J. Reynolds (Oregon State University), Shane G. Stimpson (Oak Ridge National Laboratory), Aaron M. Graham (Oak Ridge National Laboratory)
Krylov Subspace Wraps around the Two-Level p-CMFD Acceleration in the Whole-Core Transport Calculation
Nam Zin Cho (KAIST)
Presentation Video (Visible to Attendees)
Fuel Rod Analysis Programming Interface for a Tightly Coupled Multiphysics System
Alexey Cherezov (UNIST), Hanjoo Kim (Ulsan National Institute of Science and Technology), Jinsu Park (Ulsan National Institute of Science and Technology), Deokjung Lee (Ulsan National Institute of Science and Technology)
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