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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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Bipartisan Nuclear REFUEL Act introduced in the U.S. House
Peters
Latta
To streamline the licensing requirements for nuclear fuel recycling facilities and help increase investment in nuclear energy in the United States, U.S. Reps. Bob Latta (R., Ohio) and Scott Peters (D., Calif.) have introduced the bipartisan Nuclear REFUEL Act in the House of Representatives.
The bill, introduced on December 6, would amend the definition of “production facility” in the Atomic Energy Act, clarifying that a reprocessing facility producing uranium-transuranic mixed fuel would be licensed only under 10 CFR Part 70. According to the lawmakers, this single-step licensing process would significantly streamline the licensing requirements for fuel recycling facilities.
Technical Session|Experimental Reactor Physics
Monday, April 22, 2024|1:30–3:15PM PDT|Franciscan B
Session Chair:
Tomas Peltan (Research Center Rez)
Alternate Chair:
Antonin Krasa
Session Organizer:
Luka Snoj
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Reactor Pressure Vessel Characterization Methods Development for the High Flux Isotope Reactor to Support Future Vessel Replacement
1:30–1:50PM PDT
D. Chandler (ORNL), K. Burg (ORNL)
Paper
Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data
1:50–2:10PM PDT
D. Hartanto (ORNL), D. Chandler (ORNL), G. Power (ORNL), J. Bae (ORNL), K. Burg (ORNL)
Prediction of the TREAT Facility Power and Temperature of Sirius-2c Nuclear Propulsion Fuel Experiment
2:10–2:30PM PDT
Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Frederick N. Gleicher (INL), Mark DeHart (INL)
Testing and Implementation of 6% Enriched UO2 Fuel at the PULSTAR Reactor
2:30–2:50PM PDT
N.C. Fleming (NCSU), A.I. Hawari (NCSU)
Current Status of the Water Activation Loop at JSI TRIGA Reactor
2:50–3:10PM PDT
D. Kotnik (Jožef Stefan Institute), J. Peric (Jožef Stefan Institute), L. Snoj (Jožef Stefan Institute), I. Lengar (Jozef Stefan Institute)
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