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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Pui Kuan, James L. Anderson, E. L. Tolman
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 977-989
Late Paper | TMI-2: Decontamination and Waste Management / Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A27690
Articles are hosted by Taylor and Francis Online.
Thermal interaction during the Three Mile Island Unit 2 2-B coolant pump transient is considered as an explanation of the partial melting of the plenum assembly. The primary system pressure response is used to calculate the energy transferred from the reactor core to the coolant and the steam generation rate during the pump transient. The steam generation rate is then used to calculate the heating of the plenum assembly. An energy balance indicates that exothermic oxidation of Zircaloy by steam must have taken place. In calculations of plenum assembly heating, the thermal emissivity of steam is reduced to simulate the effect of hydrogen generated during the oxidation process. It is determined from the calculations that in the presence of an appreciable amount of hydrogen (∼60%), only the thin structures at the lower end of the plenum assembly would have melted, while the relatively thick structures would have been partially ablated. These results are consistent with the observed damage.
