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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 346-354
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34935
Articles are hosted by Taylor and Francis Online.
Around 200 kg of (Pu0.55 U0.45)C fuel pellets of relatively low density (86 ± 2% theoretical density) would be used as a driver fuel in the second core of the Fast Breeder Test Reactor in India. The current paper summarizes the production experience of the initial 15 kg of these fuel pellets following the “vacuum carbothermic synthesis” of tableted oxide-graphite powder mixture followed by “cold-pelletization” of carbide powder and “sintering.” The alterations made in the process equipment, radiation shielding arrangements, and fabrication parameters have been highlighted. The carbothermic synthesis and sintering were carried out in batches of 600 g and 1 kg, respectively. The percentage recovery of sintered pellets in all the batches was >90%. The resintering tests of pellets showed only marginal change in sintered density, ensuring minimum in-pile densification.
