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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.
S. Inoue, Y. Taji, Y. Nakahara, T. Suzuki
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 119-124
Technical Paper | doi.org/10.13182/NSE80-A18692
Articles are hosted by Taylor and Francis Online.
Transport of neutral particles in a toroidal plasma is treated in the same manner as that of neutrons by the Monte Carlo method. A new sampling technique of flight-path length is proposed for the torus geometry. Several routines relating to the toroidal geometry have been developed and incorporated into the neutron and gamma-ray transport Monte Carlo code “MORSE.” Results obtained from sample calculations to check the cylindrical approximation show that hot neutrals escape more easily from the torus than from the cylinder, while cold neutrals are retained better in the cylinder. Furthermore, the spectrum of the leakage neutrals is compared with the neutral and ion spectra inside the torus.
