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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|3:15–5:00PM PDT|Palos Verdes A/B
Session Chair:
Lander Ibarra (ANL)
Alternate Chair:
Milos Atz (ANL)
Session Organizer:
W. David Pointer
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MELCOR Validation Study on Sodium Pool Fire Model with Comparison to SPHINCS
David L.Y. Louie (Sandia), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)
Paper
DASSH: An Open-Source, Full-Core Subchannel Code for Fast Reactor Design and Analysis
Milos Atz (ANL), Florent Heidet (ANL)
Study on Hydraulic Characteristics in KAERI 61-PIN Wire-Wrapped Fuel Assembly Using STAR-CCM+ and ANSYS CFX
Gi-Uk Choi (Gachon Univer.), Jonggan Hong (KAERI), Yo-Han Jung (KAERI), Jae-Ho Jeong (Gachon Univer.)
Prediction of Pressure Drop in Wire-Wrapped Fuel Assemblies with Blocked Channels Using Large Eddy Simulation
D.R. Shaver (ANL), E. Merzari (ANL), L. Brockmeyer (ANL), D. Dai (ANL)
Validation of Thermal-Hydraulic Data Verification in a 37-Pin Fuel Assembly of PLANDTL Facility Using STAR-CCM+
Gi-Uk Choi (Gachon Univer.), Jae-Ho Jeong (Gachon Univer.)
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