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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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Latest News
The blossoming of cooperation between the U.S. and Canada
The United States and Canadian nuclear industries used to be an example of how two independent teams of engineers facing an identical problem—making electricity from uranium—could come up with completely different answers. In the 1950s, Canada began designing a reactor with tubes, heavy water, and natural uranium, while in the U.S. it was big pots of light water and enriched uranium.
But 80 years later, there is a remarkable convergence. The North American push for a new generation of nuclear reactors, mostly small modular reactors (SMRs), is becoming binational, with U.S. and Canadian companies seeking markets and regulatory certification on both sides of the border and in many cases sourcing key components in the other country.
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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