ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Yasunori Bessho, Takashi Nakayama, Michiro Yokomi, Katsuma Nakayama, Hiroki Sano, Nobuhiro Kanazawa
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 30-43
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2877
Articles are hosted by Taylor and Francis Online.
The steam-water power reactor core concept, originally proposed by several Russian engineers, is expected to improve natural uranium utilization through self-sustaining plutonium by using tight-lattice plutonium fuels and large void fraction two-phase flow, and to realize inherent safety characteristics through large neutron leakage from the core by a flat core configuration.Results are described for the core conceptual design for specifications meeting a 500-MW(electric) electricity supply for 13 months of continuous operation and 92 GWd/tonne fuel average discharge exposure. The design has core nuclear thermal-hydraulic characteristics that satisfy the specifications and limitations usually applied to boiling water reactors (BWRs), based on analyses by the three-dimensional multineutron-energy group diffusion analysis program CITATION. Further, its safety characteristics satisfy limitations, usually applied to BWRs, by the steam cooling emergency core cooling system and the reflood system, based on analyses of a loss-of-coolant accident, which is thought to be most critical for a core with a small water inventory, by the general transient analysis program TRAC.