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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
J. J. Sapyta, G. L. Simmons
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 508-515
Technical Paper | Shielding | doi.org/10.13182/NT75-A24451
Articles are hosted by Taylor and Francis Online.
The Sn discrete ordinates technique is used as a versatile design tool for a number of pressurized water reactor (PWR) shield design problems. This technique has been used for calculation of maximum neutron fluence at the inside wall of a reactor vessel, neutron flux distributions in steam, generators, and neutron and gamma-ray distributions at the outer surface of a reactor vessel. For vessel fluence calculations, comparisons of one-dimensional Sn and removal diffusion techniques with experiment show that the latter technique predicts higher fluences for typical PWR shield configurations. Studies of the effects of the one-dimensional approximation and different fuel management schemes show significant effects on the predicted fluence. The one-dimensional approximation gives a 20% higher fluence than the two-dimensional approximation, and the fluence can vary by as much as a factor of 2 with the type of fuel management scheme studied. Two-dimensional discrete ordinates techniques are used to determine neutron flux distributions in the energy range from 10 to 15 MeV in a steam generator that will be used for maritime reactor applications. These neutron distributions are used to calculate the source of 16N in the secondary system of the plant.