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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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.
Miguel Ceceñas-Falcón, Robert M. Edwards
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 1-11
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3100
Articles are hosted by Taylor and Francis Online.
A new test platform for stability studies is presented that can be used to generate a power time series, which in turn may be used to validate the capability of boiling water reactor stability-monitoring algorithms. The thermal hydraulics for boiling channels are modeled and coupled with neutron kinetics to analyze the nonlinear dynamics of the closed-loop system. The model uses point kinetics to study core-wide oscillations, and it couples two time-domain calculations, for the fundamental and first harmonic modes, to study out-of-phase oscillations. The channel coolant flow dynamics is dominant in the power fluctuations observed by in-core nuclear instrumentation, and additive white noise is added to the solution for the channel flow in the thermal-hydraulic model to generate a noisy power time series. Autoregressive analysis performed with the computer-generated series agrees with the stability properties of the boiling channel. The operating conditions of the channel can be modified to accommodate a wide range of stability conditions.