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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
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.
Wayne R. Zeuch, Chung-Yi Wang
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 421-432
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32578
Articles are hosted by Taylor and Francis Online.
The sodium spillage phenomenon in large liquid-metal fast breeder reactors (LMFBRs) during highly energetic hypothetical accidents has been investigated. A parametric study of the spillage process was accomplished with the ICECO code employing a control-volume method. A 1000-MW(electric) reactor, with prescribed leak paths, is modeled and analyzed during the slug impact phase. Leak paths are assumed to exist as annular penetrations in the reactor cover and as a gap at the vessel-head junction. The behavior of sodium spillage was investigated under conditions of different accident energetics, various opening cross-sectional areas, and multiple leak paths, with both stationary and moving reactor covers. Highly energetic accidents were used as the initiating events for the spillage processes described. The intent is to evaluate the range of applicability of the spillage methodology derived. It is not the intent to imply that such energetic accidents have been identified in any LMFBR safety analysis. The behavior of spillage beyond the initial transient period has also been investigated. During the transient period immediately following slug impact, it was found that spillage from annular penetrations in the reactor cover is only weakly sensitive to changes in slug velocity. The same conclusion applies to spillage from a fixed gap at the vessel-head junction. Quantity of sodium spilled during a fixed time was seen to vary proportionally with opening size. Significant sensitivity of spillage to accident energetics was seen only in cases of spillage from the vessel-head junction when the reactor cover was movable. The influence of slug impact on the motion of the reactor cover leads to the conclusion that sodium spillage is most sensitive to accident energetics inasmuch as the area of the leak path is affected. Preliminary results from sodium fire calculations indicate that spray ejection from penetrations in the reactor cover will not cause significant pressurization of the secondary containment from sodium ejected during the initial transient.
