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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|Reactor Design and Analysis
Wednesday, April 24, 2024|1:30–3:15PM PDT|Franciscan A
Session Chair:
Mehdi Asgari (ORNL)
Alternate Chair:
Joel Rhodes (Studsvik Scandpower)
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Loading Pattern Optimization for LWRs Using Monte Carlo Tree Search
1:30–1:50PM PDT
Rikuto Kasama (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.)
Paper
Scalarized Multiobjective Fuel Loading Optimization of Extended-Cycle NuScale Power Module with Evolutionary Algorithms
1:50–2:10PM PDT
Thomas Jayasankar (Univ. Michigan), Dean Price (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
Learning Nuclear Fuel Management, Case Study: Design of a Two-Year Equilibrium Cycle of a BWRX-300-like Small Modular Reactor
2:10–2:30PM PDT
Arturo Jiménez-Facio (Univ. Nacional Autónoma de México), Juan-Luis Francois (Univ. Nacional Autónoma de México)
Stochastic Optimization to Find Reference Core Configuration for Refueling Simulations of Waste-Burning Stable Salt Reactor
2:30–2:50PM PDT
Seungug Jae (Univ. Michigan), Won Sik Yang (Univ. Michigan), Thanh Hua (ANL), Yan Cao (ANL), Tom Taylor (Moltex Energy), Luke Godfrey (Moltex Energy)
First Results of Uranium Nitride Fuel Characterization Using Accelerated Fuel Qualification Process
2:50–3:10PM PDT
A. Levinsky (LANL), Z. Miller (LANL), M. Fratoni (Univ. California, Berkeley), T. Matthews (LANL), G.T. Craven (LANL), M.W.D. Cooper (LANL), V. Mehta (LANL), D.A. Andersson (LANL), J.T. Rizk (LANL)
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