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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.
I. V. Shikhovtsev et al.
Fusion Science and Technology | Volume 47 | Number 1 | January 2005 | Pages 321-323
Technical Paper | Open Magnetic Systems for Plasma Confinement | doi.org/10.13182/FST05-A677
Articles are hosted by Taylor and Francis Online.
A diagnostic neutral beam injector based on radiofrequency ion source has been developed at BINP, Novosibirsk for plasma diagnostics in magnetic fusion devices including magnetic mirrors with pulse duration up to several seconds, plasma density up to 1020 m-3 and plasma radius ~0.5m.It was observed that properties of the ceramic plasma box considerably changed after several hours of integrated operational time. After that, the proton specie in the beam essentially decreases. Eventually the proton component of the beam decreases approximately by 10% (from 60% down to 50% by current). This problem can be resolved by protection of the ceramic wall by a Faraday shield. We investigated the shield, which was made of aluminium tube with longitudinal slits and with a diameter close to that of the inner ceramic wall of the plasma box.This paper discusses the results of the beam composition measurements after installation of the Faraday shield.
