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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.
Shan H. Chien, A. R. Wazzan, D. Okrent
Nuclear Technology | Volume 60 | Number 1 | January 1983 | Pages 69-83
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33103
Articles are hosted by Taylor and Francis Online.
A fission gas code, GRABB, is developed to model intragranular and grain boundary fission gas development and release in a fast thermal transient. Transient direct electrical heating fission gas data, test 33, is simulated with GRABB and GRASS-SST. The computations show that accurate fuel modeling requires consideration of grain edge fission gas and a grain surface bubble interlinkage mechanism. Swelling data are slightly better predicted by GRABB than by GRASS-SST. Both codes underestimate the low temperature gas release data. The GRASS-SST code underestimates the intermediate temperature gas release while GRABB predictions are within the scatter of the data. The high temperature gas release is overestimated by GRASS-SST while GRABB underestimates it.
