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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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.
Raymond C. Wang, Yunlin Xu, Nathanael Hudson, Thomas J. Downar
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 504-514
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-A19437
Articles are hosted by Taylor and Francis Online.
The Special Power Excursion Reactor Test III (SPERT III) was a series of reactivity insertion experiments conducted in the 1950s. This paper describes the validation of the U.S. NRC coupled code system TRITON/PARCS/TRACE to simulate reactivity insertion accidents (RIA) using several of the SPERT III tests. The NRC coupled code system was used to perform the SPERT III E-Core configuration tests in which the RIA was initiated by the rapid ejection of a central cruciform control rod. The resulting superprompt reactivity excursion and negative Doppler reactivity feedback produced the familiar bell-shaped power increase and decrease. The energy deposition during such a power excursion has important safety consequences, and the SPERT III tests provide a validation basis for the NRC coupled multiphysics codes. The models were developed using the original experiment documentation, and the results of five separate tests were used to validate the TRITON/PARCS/TRACE coupled code system.