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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
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
Tuesday, April 23, 2024|10:15AM–12:00PM PDT|Franciscan B
Session Chair:
Ugur Mertyurek (ORNL)
Alternate Chair:
Eva E. Davidson
Session Organizer:
Brendan Kochunas (Univ. Michigan)
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Towards 2D Reference Deterministic Calculations in Support of Industrial Model Verification and Advanced Reflector Modeling Setup
10:15–10:35AM PDT
F. Inzirillo (Politecnico di Milano), A. Brighenti (Framatome), A. Cammi (Politecnico di Milano), L. Graziano (Framatome), A. Hebert (Polytechnique Montréal), G. Marleau (Polytechnique Montréal), S. Santandrea (CEA), B. Vezzoni (Framatome)
Paper
New Thermal and Leakage Synthetic Algorithms Applied to Best Estimate Schemes in Lattice Calculations
10:35–10:55AM PDT
A. Brighenti (Framatome), S. Santandrea (CEA), L. Graziano (Framatome), B. Vezzoni (Framatome)
Enhancing PWR Monte Carlo Simulations with GREAPMC: A GPU-Accelerated Approach
10:55–11:15AM PDT
Muhammad Rizwan Ali (Ulsan Nat'l Institute Science and Technology), Murat Serdar Aygul (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)
Enrichment Interpolation for High-Assay Low-Enriched Uranium Fuel Macroscopic Cross Section for Polaris/PARCS
11:15–11:35AM PDT
Junsu Kang (Univ. Michigan), Andrew M. Ward (Univ. Michigan), Ugur Mertyurek (ORNL), Thomas J. Downar (Univ. Michigan)
Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel
11:35–11:55AM PDT
Ugur Mertyurek (ORNL), Riley Cumberland (ORNL), William A. Wieselquist (ORNL)
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