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Division Spotlight
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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Latest News
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.
L. A. Zielke, R. H. Wilson
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 13-19
Technical Paper | Reactor | doi.org/10.13182/NT74-A31457
Articles are hosted by Taylor and Francis Online.
Experimental studies of pressurized-water-reactor flow and power transients are performed on a 6-ft-long electrically heated 9-rod bundle in a square array. Flow transients are patterned after decay rates typical of reactor coolant pump coast-downs. Power transients are approximately 5% ramp increases. For the transient conditions tested, there is no premature occurrence of critical heat flux. Steady-state critical heat flux data for axial spacer grid separations of 10, 15, and 21 in. indicated there is no grid-spacing effect on critical heat flux by the Babcock & Wilcox Mark B2-style spacer grid at normal reactor flow rates.
