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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.
Kenji Yokoyama, Akira Shono, Makoto Ishikawa
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 249-263
Technical Paper | doi.org/10.13182/NSE06-109
Articles are hosted by Taylor and Francis Online.
Experimental data acquired during experimental fast reactor JOYO MK-I performance tests in the late 1970s have been reevaluated and analyzed with a nuclear analysis system for fast reactors employed by the Japan Atomic Energy Agency. For the purpose of improving the prediction accuracy of nuclear characteristics, nominal values and uncertainties of the experimental data were reevaluated in light of knowledge obtained after the MK-I performance test and calculation results based on the latest reactor physics analysis methods. All nominal values were corrected by a formulation of control rod interaction effects proposed in the present paper, and all possible uncertainty factors were evaluated and quantified.The analysis results agreed well with measured values within the experimental and nuclear-induced uncertainties for all the nuclear characteristics of criticality, control rod worth, sodium void reactivity, fuel replacement reactivity, and isothermal temperature coefficient.Meanwhile, the present reevaluated data have been registered with the International Reactor Physics Benchmark Experiments Project with the expectation that these data will be widely used.
