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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Technical Session|Sponsored by MSTD
Wednesday, November 16, 2022|10:00–11:45AM MST|Kaibab
Session Chair:
Annabelle Le Coq
Alternate Chair:
Jake R. Quincey
Session Organizer:
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Effective Thermal Conductivity of UO2-Metal Platelet Composites
10:00–10:20AM MST
JangSoo Oh (KAERI), YongSik Yang (KAERI), JaeYong Kim (KAERI)
Paper
Experimental Investigation of Degradation Mechanisms in ATF Coated Cladding Under Transient Conditions
10:20–10:40AM MST
Hwasung Yeom (Univ. Wisconsin, Madison), Tyler Dabney (Univ. Wisconsin, Madison), David Kamerman (INL), James Corson (U.S. Nuclear Regulatory Commission), Brent Heuser (Univ. Illinois, Urbana-Champaign), Kumar Sridharan (Univ. Wisconsin, Madison)
Neutronics Assessment of Advanced Fuel Claddings in the Equilibrium LWR Core Design
10:40–11:00AM MST
Kingsley Ogujiuba (NCSU), Khang Hoang Nhat Nguyen (NCSU), Yong-Joon Choi (INL), Jason Hou (NCSU)
Neutronic Analysis of Novel Accident Tolerant Control Blade in Boiling Water Reactor (BWR) Core
11:00–11:20AM MST
Arnold Pradhan (Univ. Idaho), Indrajit Charit (Univ. Idaho)
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