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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
Trio of GAIN vouchers for sensors, materials, and fuels testing
The Department of Energy announced on June 5 that three companies—all of which are new to the Gateway for Accelerated Innovation in Nuclear (GAIN) voucher program—will receive vouchers to support their research on advanced fuels, materials, and sensors. The second round fiscal year 2025 vouchers will let the companies access specialized research facilities and expertise in the DOE’s national laboratory complex.
C. M. Sommer, W. M. Stacey, B. Petrovic
Nuclear Technology | Volume 172 | Number 1 | October 2010 | Pages 48-59
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10881
Articles are hosted by Taylor and Francis Online.
A fuel cycle analysis was performed for the SABR transmutation reactor concept, using the ERANOS fast reactor physics code. SABR is a sodium-cooled, transuranic (TRU)-Zr-fueled, subcritical fast reactor driven by a tokamak fusion neutron source. Three different four-batch reprocessing fuel cycles, in which all the TRUs from spent nuclear fuel discharged from light water reactors are fissioned to >90% (by recycling four times), was examined. The total fuel residence time in the reactor was limited in these three cycles by a radiation damage limit (100, 200, or 300 displacements per atom) to the cladding material. In the fourth cycle the fuel residence time was determined by trying to achieve 90% burnup in a once-through cycle without reprocessing.