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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
Yousri Elkassabgi, Graydon L. Yoder, Wallace R. Gambill
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 411-420
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34940
Articles are hosted by Taylor and Francis Online.
The Advanced Neutron Source Reactor (ANSR) is being designed to become the world’s most advanced reactor for neutron scattering research. It is both moderated and cooled by heavy water (D2O) and uses a core of highly enriched uranium silicide fuel in a plate geometry. During the refueling process of the ANSR, the spent fuel must be moved from within the primary coolant loop (containing D2O), through a pool of D2O, and finally into a light water spent-fuel storage area. This is accomplished by using a refueling tunnel and fuel transfer cask or lock. Some means of cooling the core, using either natural circulation or forced convection, must be accommodated during this process. Several thermal-hydraulic aspects of this refueling process have been studied. A modified version of the NATCON computer code developed at Argonne National Laboratory was used for the analysis. The NATCON code was revised and modified to incorporate improved friction and heat transfer correlations, and routines for the physical properties of D2O were added. The revised code can also accommodate a two-dimensional power density distribution. The results for the refueling process design show that ∼48 h is required to ensure the no-boiling condition. The addition of a short chimney reduces that time to ∼12 h.
