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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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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.
Shih-Jen Wang, Ming-Song Lin
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 156-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34553
Articles are hosted by Taylor and Francis Online.
The characteristics of xenon dynamics are simulated, and related parameters are identified in the Taiwan Research Reactor. A xenon transient for a 20% stepwise decrease from 85.6% rated power is performed and simulated with design data. The trends in the moderator levels are similar in the test and in the simulation. However, there are discrepancies in the magnitude and shape. Because no reactivity feedback occurs for 2 h after the power change, except for xenon poisoning, a parameter optimization method is applied to identify the migration area and the initial neutron flux by minimizing the integrated square error of the moderator level from 2 to 20 h after the power change. The optimized moderator level fit the test result very well, and the identified parameters are reasonably close to the experimental data.