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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NDA funds Plutonium Ceramics Academic Hub with U.K. universities
The United Kingdom’s Nuclear Decommissioning Authority has announced that it will establish a Plutonium Ceramics Academic Hub with the Universities of Manchester and Sheffield. The announcement follows a decision by the U.K. government in January to immobilize the country’s inventory of civil separated plutonium at the Sellafield nuclear site, mitigating the material’s long-term safety and security risks.
Technical Session|Methods
Wednesday, April 24, 2024|3:30–5:15PM PDT|Continental Ballroom 1
Session Chair:
Kazuya Yamaji (Mitsubishi Heavy Industries)
Alternate Chair:
Kyoung Lee (ORNL)
Session Organizer:
Go Chiba (Hokkaido University)
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Pathline Reformulation of the Delayed Neutron Precursors Equation
3:30–3:50PM PDT
Mathis Caprais (CEA), Daniele Tomatis (newcleo), Nathan Greiner (CEA), André Bergeron (CEA)
Paper
Presentation Slides (Visible to Attendees)
Transport of Highly Volatile Gases Related to Noble Gases and Tritium in the MSRE
3:50–4:10PM PDT
Kyoung O. Lee (ORNL), David Kropaczek (ORNL), Jorge Navarro (ORNL)
Nuclear Heating Benchmark in Molten Salt Fast Reactor
4:10–4:30PM PDT
A. Chambon (Technical Univ. Denmark), E.P. Senstius (Technical Univ. Denmark), N. Moret (Technical Univ. Denmark)
Benchmarking Between Fuel Cycle Codes and Nuclear Data Evaluations for Decay Heat After a Uranium-233 Fission Pulse
4:30–4:50PM PDT
Riko Okuyama (Hokkaido Univ.), Go Chiba (Hokkaido Univ.), Sebastien Lahaye (CEA)
A Numerical Study of the Similarity Between the Decay Heat of PWR and SFR MOX Fuels
4:50–5:10PM PDT
D. Da Cunha (CEA), J.-F. Lebrat (CEA), F. Nguyen (CEA), V. Vallet (CEA)
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