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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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A series of firsts delivers new Plant Vogtle units
Southern Nuclear was first when no one wanted to be.
The nuclear subsidiary of the century-old utility Southern Company, based in Atlanta, Ga., joined a pack of nuclear companies in the early 2000s—during what was then dubbed a “nuclear renaissance”—bullish on plans for new large nuclear facilities and adding thousands of new carbon-free megawatts to the grid.
In 2008, Southern Nuclear applied for a combined construction and operating license (COL), positioning the company to receive the first such license from the U.S. Nuclear Regulatory Commission in 2012. Also in 2008, Southern became the first U.S. company to sign an engineering, procurement, and construction contract for a Generation III+ reactor. Southern chose Westinghouse’s AP1000 pressurized water reactor, which was certified by the NRC in December 2011.
Fast forward a dozen years—which saw dozens of setbacks and hundreds of successes—and Southern Nuclear and its stakeholders celebrated the completion of Vogtle Units 3 and 4: the first new commercial nuclear power construction project completed in the U.S. in more than 30 years.
Adam Zabriskie, Sebastian Schunert, Daniel Schwen, Javier Ortensi, Benjamin Baker, Yaqi Wang, Vincent Laboure, Mark DeHart, Wade Marcum
Nuclear Science and Engineering | Volume 193 | Number 4 | April 2019 | Pages 368-387
Technical Paper | doi.org/10.1080/00295639.2018.1528802
Articles are hosted by Taylor and Francis Online.
The restart of the Transient Reactor Test facility (TREAT) will once again provide the capability for rapid transient testing of fuel concepts. Under the auspices of the U.S. Department of Energy’s Office of Material Management and Minimization, research is underway to assess the feasibility of converting the current high-enriched uranium (HEU) fuel in TREAT to low-enriched uranium (LEU) fuel. The LEU concept retains the fuel process that results in micrometer-sized UO2 fuel grains dispersed in a graphite moderator matrix. The LEU fuel design includes more 238U, which fundamentally changes the feedback mechanisms in the fuel. To explore the effects of conversion on a pulse transient, a simplified semi-infinite TREAT fuel element model of both the HEU and proposed LEU configurations was simulated using MAMMOTH with the requisite multiscale and multiphysics coupling. The developed method incorporates fission energy deposition at microscale locations from the Mesoscale Atomistic Glue Program for Integrated Execution (Magpie), heterogeneity effects from the microscale model in the form of time lag, and independent feedback temperature sources from the microscale fuel grain model and surrounding moderator. The fuel grain size was varied along with temperature feedback sources to explore the feedback mechanisms. Significant differences between fuel and graphite temperatures were found to develop for transients with large energy depositions, for large fuel grains, and for fission-fragment irradiated graphite. These differences in temperature do not influence the feedback for HEU fuel but have a significant effect on LEU fuel. The difference between HEU and LEU fuel is caused by the fuel temperature feedback coefficient for LEU fuel that is roughly 20% of the graphite temperature feedback coefficient. The immediate equilibrium assumption is invalid for LEU fuel in certain TREAT operating regimes. As the conversion of TREAT to LEU fuel aims to conserve HEU capabilities, MAMMOTH simulations of the LEU model explore the effects of matching the same period, peak power density, and deposited energy of the HEU model. The same pulse shape was not achievable due to the feedback mechanism changes.
