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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.
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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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Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Mohamed E. Sawan
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 766-770
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9002
Articles are hosted by Taylor and Francis Online.
Data for 40 of the 71 isotopes/elements in FENDL-2.1 were taken from ENDF/B-VI.8. Following the release of ENDF/B-VII.0 we performed a preliminary assessment for changes made in data of these 40 isotopes/elements. We compared the relevant cross sections in the two libraries. In addition, we carried out MCNP calculations for a calculational benchmark representative of an early ITER design that was utilized during the FENDL development process. In addition, we performed 3-D calculations for an inertial fusion power plant conceptual design. It is concluded that modifying FENDL-2.1 to include the most recent ENDF/B-VII.0 is not urgently needed for ITER analysis. On the other hand, the larger changes in calculated ICF target neutronics parameters and tritium breeding ratio confirm the need for updating FENDL-2.1 for use in analysis of fusion systems beyond ITER. Additional calculations are in progress for integral experimental benchmarks to fully understand the impact of data changes introduced in ENDF/B-VII.0.
