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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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.
Constantine P. Tzanos
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 662-673
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32811
Articles are hosted by Taylor and Francis Online.
Maximum cladding temperatures in heterogeneous liquid-metal fast breeder reactors (LMFBRs) can be reduced if the flow allocation between core and blanket assemblies is continuously varied during burnup. An analytical model has been developed that optimizes the time variation of the flow such that the reduction in maximum cladding temperatures is maximized. In addition, the concept of continuously varying the flow allocation between core and blanket assemblies has been evaluated for different fuel management schemes in a low sodium void reactivity 3000-MW heterogeneous LMFBR. This evaluation shows that (a) the reduction in maximum cladding midwall temperatures is small (~10°C) if the reactor is partially refueled at the end of each burnup cycle (cycle length of one year), and (b) this reduction is increased to 20°C if a straight burn fuel scheme is used with a core and internal blanket fuel residence time of two years.