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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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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Lightbridge, Centrus to conduct study for pilot fuel fabrication plant
Signing CEOs: Centrus’s Daniel Poneman, left, and Lightbridge’s Seth Grae. (Photo: Lightbridge/X)
Nuclear fuel companies Lightbridge Corporation and Centrus Energy have announced a contract to conduct a front-end engineering and design (FEED) study to add a dedicated Lightbridge Pilot Fuel Fabrication Facility (LPFFF) at Centrus’s American Centrifuge Plant in Piketon, Ohio.
Lightbridge chief executive officer Seth Grae and Centrus CEO Daniel Poneman inked the agreement yesterday at the COP28 conference, currently underway in the United Arab Emirates.
The FEED study, according to the joint announcement, will identify infrastructure and licensing requirements as well as the estimated cost and construction schedule for the LPFFF. Centrus’s wholly owned subsidiary, American Centrifuge Operating, will lead the study, which is expected to be completed sometime next year.
Technical Session|Sponsored by RPD
Monday, November 14, 2022|3:15–5:00PM MST|Sonoran 7
Jason Hou (NCSU)
Massimiliano Fratoni (UC Berkeley)
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Open-Source Computational Model of a Molten Chloride Fast Reactor
Harrison Reisinger (Univ. Tennessee, Knoxville), C. Erika Moss (Univ. Tennessee, Knoxville), Nathaniel Howard (Univ. Tennessee, Knoxville), Maxwell Wagner (Univ. Tennessee, Knoxville), Peyton Mann (Univ. Tennessee, Knoxville), Ondrej Chvala (Univ. Tennessee, Knoxville)
Molten Salt Reactor Modeling in SCALE: Effects of Multigroup Libraries on Depletion Analysis
Christopher E. Bayne (Georgia Tech), Bojan Petrovic (Georgia Tech)
MSR Reactivity, Power, and Inventory Simulations with SCALE
Friederike Bostelmann (ORNL), Austin Lo (ORNL), Benjamin R. Betzler (ORNL), Donny Hartanto (ORNL), William A. Wieselquist (ORNL)
Parametric Study of the Thorium-Based Molten Salt Reactor Core
Seda Yilmaz Kaygisiz (Purdue), Shripad Revankar (Purdue)
MSRE Transient Benchmark Development and Evaluation: NEUP Project Updates
Zeyun Wu (Virginia Commonwealth Univ.), Mohamed Elhareef (Virginia Commonwealth Univ.), Massimiliano Fratoni (Univ. California, Berkeley), Benjamin Betzler (ORNL), Tingzhou Fei (ANL), Kurt Harris (Flibe Energy)
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