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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
Jun 2025
Jan 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
Nuclear fuel cycle reimagined: Powering the next frontiers from nuclear waste
In the fall of 2023, a small Zeno Power team accomplished a major feat: they demonstrated the first strontium-90 heat source in decades—and the first-ever by a commercial company.
Zeno Power worked with Pacific Northwest National Laboratory to fabricate and validate this Z1 heat source design at the lab’s Radiochemical Processing Laboratory. The Z1 demonstration heralded renewed interest in developing radioisotope power system (RPS) technology. In early 2025, the heat source was disassembled, and the Sr-90 was returned to the U.S. Department of Energy for continued use.
Technical Session|Sponsored by Integrated Phenomena in Reactor Materials
Thursday, December 14, 2023|10:00–11:40AM CST|Galerie 5
Session Chair:
Bruce A. Pint (ORNL)
Alternate Chair:
Stuart A. Maloy (PNNL)
Track Organizers:
Andrew Hoffman (n/a)
Adrian Couet (University of Wisconsin- Madison)
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Impact of Proton Irradiation on Corrosion Behavior of Zircaloy-4 and Zr-1Nb Alloys in Hydrogenated Water: A Post-Irradiation Study
10:00–10:20AM CST
Peng Wang (Univ. Michigan), Gary S. Was (Univ. Michigan)
Paper
In-situ Irradiation and Elastic Stress Effects on Molten Fluoride Salt Corrosion of Structural Alloys
10:20–10:40AM CST
C. Evered (Univ. Wisconsin, Madison), M. Tonks (Univ. Florida), K. Sridharan (Univ. Wisconsin, Madison), A. Couet (Univ. Wisconsin, Madison)
Molten Chloride Salt Corrosion of Ultra-High Temperature Ceramics
10:40–11:00AM CST
Brian Carpman (Univ. Michigan), James Kelly (Univ. Michigan), Stephen S. Raiman (Univ. Michigan)
Microstructure and Mechanical Properties of Novel Nickel-Base Alloys for Molten Salt Reactor Applications
11:00–11:20AM CST
Ryan Thier (Univ. Tennessee, Knoxville), Jaimie Tiley (ORNL), Bruce Pint (ORNL), Ryan Gordon (Univ. Wisconsin, Madison), Kumar Sridharan (Univ. Wisconsin, Madison), Soumya Nag (ORNL), Steven Zinkle (Univ. Tennessee, Knoxville)
Design of Functionally-Graded Cermet Coatings for Molten Salt Reactors by High Throughput Finite Element Modeling
11:20–11:40AM CST
K. Yan (Rensselaer Polytechnic Institute), D. Zhao (Rensselaer Polytechnic Institute), S. Sarkar (Rensselaer Polytechnic Institute), R.Rahul (Rensselaer Polytechnic Institute), J. Lian (Rensselaer Polytechnic Institute)
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