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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.
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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.
T. Oishi, K. Yamazaki, Y. Hori
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1113-1116
Concept and Facility | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12610
Articles are hosted by Taylor and Francis Online.
To model the fuel supply in nuclear fusion reactors with D-T burning plasmas, the relationship among the D/T fuel ratio, tritium consumption, and reactor output power is analyzed numerically using the TOTAL (toroidal transport analysis linkage) simulation code. In the case that a deuterium-rich pellet is employed, the amount of tritium to be injected to the reactor as the fuel can be reduced compared with the case when the D to T ratio is the same. The fusion output power can be adjusted by controlling the D/T ratio while the electron density is fixed. This control method of the output power by D/T ratio scan can save the tritium consumption compared with that by the density scan, especially in the cases with lower fusion output power.