ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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!
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January 2025
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December 2024
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November 2024
Latest News
Matthew Marzano confirmed as newest NRC commissioner
A nuclear engineer, former reactor operator, and nuclear navy educator earned U.S. Senate approval today to take a seat on the Nuclear Regulatory Commission.
Matthew Marzano was confirmed in a 50–45 vote in the Senate and steps into an existing five-year term that will expire June 30, 2028. He joins the five-member commission, which has been without a tiebreaker vote since June 2023, when Jeff Baran’s term expired.
Marzano brings more than a decade of industry experience both working in nuclear plants and advising energy policy on Capitol Hill.
Workshop
Thursday, April 8, 2021|11:45AM–1:00PM EDT
Session Chair:
Agustin Abarca
Alternate Chair:
Maria N. Avramova
Session Organizer:
Edward Chen (NC State Univ.)
Track Organizer:
Session Producers:
Jacob Weinberg (NCSU)
This workshop gives an overview of the advanced thermal-hydraulic sub-channel code CTF and its nuclear fuel rod solver CTFFuel. The code is used for steady state and transient design and safety analyses of current and advanced nuclear reactors. CTF is also the thermal-hydraulic component of the CASL-developed Virtual Environment for Reactor Applications (VERA) core simulator used for thermal feedback and prediction of thermal-hydraulic safety parameters. The international CTF users’ group has currently more than 60 member-organizations from different countries including industry, regulation, national labs, consulting companies, research institutes and academia. The theory and physics models of CTF/CTFFuel will be presented first, followed by an interactive real-time demonstration on how to build fuel assembly and core models, execute the code in a serial and a parallel mode, and post process the results using different available tools.
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