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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.
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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.
John R. White, Thomas F. DeLorey
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 129-147
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34551
Articles are hosted by Taylor and Francis Online.
A detailed sensitivity and uncertainty analysis is performed for several parameters of interest in the design of the high-conversion reactor (HCR) concept. The main goals of this work are to determine the response standard deviation due to basic nuclear data uncertainties and to incorporate integral experiment information from the PROTEUS facility to reduce the computed uncertainties, where possible. The results for reactivity and five important reaction rate ratios (at the 0% void state) that are part of the measurement program in the PROTEUS phase II experiments are highlighted. In addition, the void coefficient at both low void and high void is studied. The computed correlation coefficients between the PROTEUS and HCR models are uniformly high for all responses. This indicates that a reduction in uncertainty can be achieved within the measurement uncertainty and that the PROTEUS experiments were ideal for the physics characterization of HCR responses.