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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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Prepare for the 2025 Nuclear PE Exam with ANS guides
The next opportunity to earn professional engineer (PE) licensure in nuclear engineering is this fall, and now is the time to sign up and begin studying with the help of materials like the online module program offered by the American Nuclear Society.
Mitsuo Shindo, Akira Tsuruo, Shun-ichi Miyasaka, Mitsuyuki Kitazume, Jun-ichi Miyakoshi
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 450-463
Technical Paper | doi.org/10.13182/NSE67-A18284
Articles are hosted by Taylor and Francis Online.
The transmission of gamma rays through a straight cylindrical duct from an infinite plane source has been studied both theoretically and experimentally. The distribution of the resulting dose in the vicinity of the duct was calculated by the ray-analysis method, with the exception that the dose arising from radiation scattered within the duct was calculated by a semi-analytical Monte Carlo method. These results, together with those from experiments, lead to useful conclusions. Data applicable to the design of small ducts through shields have been developed for a range of various geometric parameters.
