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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.
B. Smith, P. Wilson, M. Sawan, T. Bohm
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 57-62
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8876
Articles are hosted by Taylor and Francis Online.
Radiation shielding, thermal protection, and energy removal for ITER are provided by an array of firstwall/shield modules (FWS). Nuclear analysis of the shield modules is important for understanding their performance and lifetime in the system. Using Direct Accelerated Geometry (DAG)-MCNPX, a coupling of traditional MCNPX with the Common Geometry Module (CGM) and the Mesh Oriented dAtaBase (MOAB) developed at UW, high-fidelity 3-D neutronics analysis is now possible. Particles are transported in the CAD geometry reducing analysis time, eliminating input error, and preserving geometric detail. The surface source read-write capability that exists in MCNPX has been used in DAG-MCNPX to combine realistic source conditions with an efficient analysis model. A surface source was written using a 3-D model of ITER with a detailed plasma source. The surface source was then used in a detailed 3-D CAD model of Module 13.3-D high fidelity mesh tallies were used to calculate nuclear heating used in thermal-hydraulics analysis. Surface source results were compared against results using a hybrid 1-D/3-D approach in which a uniform neutron source is extended infinitely in the vertical direction. Results show that the hybrid source overestimated the total number and under estimated the average energy of particles incident on the FW. The hybrid approach was found to overestimate the nuclear heating at the front of the first wall by as much as 63%.
