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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
H. Maekawa, S. Yamaguchia, C. Konno, Y. Oyama, Y. Ikeda, K. Sekiyamab, K. Kosako
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1949-1954
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29627
Articles are hosted by Taylor and Francis Online.
An integral experiment was performed on a Be cylindrical assembly of 630mm in diameter and 456mm in thick. Measured items were reaction rates, in-system neutron spectra and gamma-ray heating rates. The experimental analysis was performed by the MCNP and DOT3.5 codes using the nuclear data of JENDL-3, JENDL-3PR1, ENDF/B-IV and LANL. For high threshold reactions and integral flux above 10MeV, the calculation based on JENDL-3 agrees well with the experiment, while the calculations of ENDF/B-IV and LANL underestimetes those compared to the experiment. For integral neutron flux of 0.16∼0.5 MeV, the calculation of JENDL-3 agrees well with the experiment. But in the case of ENDF/B-IV the underestimation is 20%. It can be concluded that the nuclear data of Be in JENDL-3 improves very much in accuracy from the temporary version JENDL-3PR1.
