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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Patrick G. Boyle, Daniel E. Hughes, Samuel H. Levine
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 222-230
Technical Note | Fission Reactors | doi.org/10.13182/NT98-A2894
Articles are hosted by Taylor and Francis Online.
The Pennsylvania State University Breazeale (TRIGA) Reactor (PSBR) has operated for 25 yr (440 MWd) using a mixed 12 wt% ZrHx-U and 8.5 wt% ZrHx-U fuel configuration (both enriched to 20 wt% 235U, and x, the ratio of H to Zr, is nominally 1.65). In this configuration, the most reactive 12 wt% ZrHx-U fuel is always in the B-ring. The B-ring is the innermost hexagonal ring, incorporating 6 fuel elements, and the C-ring is the next outward ring, having 12 fuel elements. PSBR experience during pulsing and steady-state operation indicates that with these configurations the maximum fuel temperatures should be reduced in order to extend the useful life of the 12 wt% ZrHx-U fuel. This is because during the past 10 yr, the fuel temperatures of the new fuel have been significantly higher than the original fuel. The instrumented fuel element (I-15) loaded into the core ~10 yr ago and the most recent batch of fresh 12 wt% ZrHx-U fuel elements (six total, including I-16 and I-17) measured temperatures more than 100°C higher than any previous instrumented fuel element. Subsequent pulsing of I-15 increased its measured fuel temperature to where it began to approach the limiting safety system setting. Recent pulsing of I-16 and I-17 caused their steady-state fuel temperatures to decrease slightly, but they remain high. The new fuel management plan reduces these fuel temperatures by replacing the used 12 wt% ZrHx-U fuel in the C-ring with fresh 12 wt% ZrHx-U fuel. The 12 wt% ZrHx-U fuel in the B-ring is replaced with 8.5 wt% ZrHx-U fuel. Experiments have been performed to verify the predicted core parameters for the new plan. The lifetime of the new 12 wt% ZrHx-U fuel should now be limited by its maximum allowed burnup, which has not occurred so far.
