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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
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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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Latest News
Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
J. C. Westmoreland
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 533-546
Technical Paper | doi.org/10.13182/NSE57-A25423
Articles are hosted by Taylor and Francis Online.
An analysis of compact natural circulation steam generators for nuclear power plants has been made to facilitate the prediction of certain dynamic characteristics of the systems in terms of their pertinent geometric parameters. A simple two-phase annular flow model is proposed to permit analytical solutions for the thermal driving head and friction pressure loss in the riser. The results of this model have been interpreted in terms of the Martinelli correlation and a favorable comparison is presented. The equations from the analysis have been programmed for solution by the IBM 650 digital computer and several steam generator configurations studied with regard to geometric parameters and also thermodynamic operating state. The main consequence of rapid power changes with these specific units is the carryover of moisture to the turbines which implies adequate separator margin can not be provided for. The capability of the evaporator to supply adequate steam for any desired power change has not been questioned; however, it is noted that a reduction in downcomer flow during a transient could reduce its capacity to do so.
