ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Björn Gylling, Luis Moreno, Ivars Neretnieks
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 93-103
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2854
Articles are hosted by Taylor and Francis Online.
The release from initially damaged canisters for spent fuel located in crystalline rock is calculated. The radionuclide transport through the near field is calculated using the compartment model (NUCTRAN), and then the channel network concept (CHAN3D) is used for the transport in the far field. The flow rates at certain canister locations from the flow field generated by CHAN3D are used as input data to NUCTRAN, and then the near-field release is used as input to the far-field transport simulations. The models are applied to a hypothetical repository layout located at the Swedish Äspö Hard Rock Laboratory site. The hydraulic data and the flow-wetted surface area used in the model are estimated from hydraulic measurements. Release rate calculations for several radionuclides are performed to illustrate the model-coupling concept. The coupled models can be used as an efficient tool to simulate release from a repository and the transport to a recipient.