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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
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.
Steven E. Aumeier, John C. Lee, Derek M. Cribley, William R. Martin
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 299-319
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35014
Articles are hosted by Taylor and Francis Online.
We present a new time-based cross-section parameterization scheme that allows for a more accurate global depletion analysis than current methodologies without requiring major modifications to existing codes. The new cross-section parameterization scheme makes use of few-group macroscopic cross sections calculated as a function of time at several different power levels. These cross sections are block ordered by time rather than exposure to allow for the explicit representation of instantaneous control, i.e., soluble boron concentration, and thus accurate isotopic history, within the base cross-section library. The scheme is applied to a global depletion analysis of the Slightly Enriched Spectral-Shift Reactor, an advanced converter reactor based on a pressurized water reactor design, using the CPM-2 assembly-level collision probability code and the UM2DB two-dimensional diffusion code. The depletion calculation establishes the feasibility and potential advantages of the proposed cross-section parameterization methodology and shows that through a judicious choice of spectral shift control rod withdrawal strategies, it is possible to substantially increase fuel resource utilization via the spectral shift effect while maintaining acceptable power peaking factors.
