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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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Fusion Science and Technology
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.
Viatcheslav V. Anisimov, Emanuela Cavalleri, Fedor I. Karmanov, Victor I. Slobodtchouk, Lioudmila N. Latysheva, Igor A. Pshenichnov, Marcello Vecchi
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 219-227
Technical Paper | doi.org/10.13182/FST01-A163
Articles are hosted by Taylor and Francis Online.
Design calculations of thermohydraulic parameters of the secondary target of the intense neutron source (INS) based on muon-catalyzed fusion (CF) (the CF-INS) are presented for a liquid deuterium-tritium (D-T) mixture. The synthesizer is connected to an external cooler by input and output pipelines. The optimal mixture composition, synthesizer layout, and dimensions are determined. The possibility of creating a D-T mixture flow with a quasi-uniform velocity distribution is demonstrated. Possible vortexes were found to be eliminated by installation of corresponding hydraulic resistance in the shape of a spherical shell segment. At the CF-INS operation with its design parameters [neutron flux as high as 1014 n/(cm2s)], the total heat deposit in the D-T mixture due to fusion and charged-particle ionization losses is estimated at ~117 kW. However, even at such conditions, with the appropriate synthesizer geometry and mass flow rate, the mixture temperature does not exceed the boiling point in any part of the synthesizer.
