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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
Hartwig Laue, Klaus Hermann Kerz
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 46-52
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33372
Articles are hosted by Taylor and Francis Online.
Within the framework of the licensing procedure for the SNR-300 nuclear power plant in Kalkar, Federal Republic of Germany, it is verified that the reactor vessel and its internal component parts withstand the loadings resulting from a hypothetical core disruptive accident (HCDA). The resultant high temperatures at the areas in contact with molten nuclear fuel are sufficiently reduced by the decay heat removal chain so that these component parts can withstand the mechanical forces resulting from the dead weight of the fuel and the adjacent component parts. The finite element method is used for determination of strain resulting from mechanical loadings and thermal expansion for the strength test and for evaluation of the component parts concerned according to the applicable rules for this type of accident, taking into consideration criteria and stress limit values.
