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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.
O. K. Tallent, R. P. Wichner, Roy L. Towns
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 336-343
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33579
Articles are hosted by Taylor and Francis Online.
The transport or diffusion of uranium (as a stand-in for plutonium) was investigated under conditions approximating those of the primary coolant loop in a high-temperature gas-cooled reactor. Profiles were obtained for uranium penetration in H-451 graphite at temperatures ranging from 900 to 1400°C. Profile data for given temperatures were considered in terms of the following expression: where C is the concentration of uranium at time t, for distance x, into the pellet; C0 is a constant representing the uranium concentration at x = 0 for all t, and D is the diffusion coefficient. Diffusion coefficients for uranium initially present as dicarbide at 1000 and 1400°C were found to be defined byFor uranium initially present as dioxide at 900, 1000, and 1400°C, diffusion coefficients are defined bywhere R is the gas constant and T is the temperature in degrees Kelvin.