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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.
To access the session recording, you must be logged in and registered for the meeting.
Register NowLog In
To access session resources, you must be logged in and registered for the meeting.
To join the conversation, you must be logged in and registered for the meeting.
