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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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.
Garry C. Gose, John G. Shatford, Lance J. Agee
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 132-145
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2857
Articles are hosted by Taylor and Francis Online.
A RETRAN-03 computer code version has been developed to analyze reactor transients requiring three-dimensional reactor core neutronics models. The new code will enable the user to couple a complex RETRAN nuclear steam supply system model to a detailed multidimensional neutronics core model.The neutronics model is based on a three-dimensional nodal model using the analytic nodal method that allows a detailed three-dimensional representation of the core but requires less computational effort than conventional fine-mesh finite difference methods. The model uses a full two-group diffusion equation implementation coupled to six delayed neutron groups.Two representative analyses were used as evaluation cases. The work involved the first use of the RETRAN-03 advanced system analysis code using three-dimensional neutronics methods. The purpose of these studies was to gain experience in RETRAN-3D modeling methods and to compare the results with previous calculations as part of a code verification effort.The work has led to a new capability for the RETRAN-03 code, enabling the user to examine the core behavior in more detail than in previous versions and to study transients that involve nonsymmetric core behavior.