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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Technology
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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.
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
Nuclear Technology | Volume 206 | Number 5 | May 2020 | Pages 663-696
Critical Review | doi.org/10.1080/00295450.2019.1698257
Articles are hosted by Taylor and Francis Online.
Flow and thermal performance analysis is an important area in the nuclear industry for the safe operation of reactors and the optimum design of fuel rod bundles with spacers in the reactor core. The spacer, an essential element in the nuclear fuel rod assembly, is used to support the fuel rods in the bundle and maintain suitable clearance between the rods. This paper represents a comprehensive review of the effects of spacer/mixing vane spacer on flow behavior and heat transfer performance in nuclear fuel rod bundles, annular channels, and circular tubes. This paper is based on the experimental and computational fluid dynamics (CFD) investigations performed by researchers in literature for both single-phase and two-phase fluid flow. In addition, the effects of some parameters, such as Reynolds number, hydraulic diameter, pitch-to-diameter ratio, blockage ratio, working fluid, and number of fuel rods in an assembly, on flow and thermal performance analysis have been reviewed. A detailed review has been carried out by considering both experimental and CFD methods used in the past for analysis of thermal-hydraulic performance in the fuel channels of nuclear reactors.