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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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April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Ji-Feng Wang, Tsuneo Amano, Yuichi Ogawa, Nobuyuki Inoue
Fusion Science and Technology | Volume 32 | Number 4 | December 1997 | Pages 590-600
Technical Paper | Special Section: Plasma Control Issues for Tokamaks / Plasma Engineering | doi.org/10.13182/FST97-A19906
Articles are hosted by Taylor and Francis Online.
The dynamics of burning plasma for various transient situations in International Thermonuclear Experimental Reactor (ITER) plasma have been simulated with the 1½-dimensional up-down asymmetry Tokamak Transport Simulation code. Attention is paid primarily to intrinsic plasma transport processes such as confinement improvement and changes of plasma profiles. A large excursion of fusion power is shown to take place with a small improvement of plasma confinement; e.g., an increase of the global energy confinement by a factor of 1.2 yields a fusion power excursion of ∼30% within a few seconds. Given this short timescale of the fusion power transient, any feedback control of fueling deuterium-tritium gas is difficult. The effect of plasma profile on fusion power excursion is studied by changing the particle transport denoted by the peaking parameter Cv. When the fusion power excursion is mild and slow, the feedback control is quite effective in suppressing the fusion power excursion and in shortening the duration time of the power transient. Changes of the pumping efficacy are also studied, and large excursions of fusion power are not observed because of a decrease of the fuel density itself when the pumping efficacy is increased; and helium ash accumulates in the case of a decrease of the pumping efficacy. Finally, magnetohydrodynamic sawtooth activity leads to a fusion power fluctuation of ±20%, although such activity is helpful for helium ash exhaust.