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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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ANS’s Mentor Match applications open
Applications are now open for the American Nuclear Society’s newly redesigned mentoring program. Mentor Match is a unique opportunity available only to ANS members that offers year-round mentorship and networking opportunities to Society members at any point in their education.
The deadline to apply for membership in the inaugural summer cohort, which will take place July 1–August 31, is June 20. The application form can be found here.
J. F. Kunze, G. D. Pincock, R. E. Hyland
Nuclear Technology | Volume 6 | Number 2 | February 1969 | Pages 104-115
Technical Paper and Note | doi.org/10.13182/NT69-A28241
Articles are hosted by Taylor and Francis Online.
The cavity reactor concept consists of a core, generally of dilute fuel, surrounded by a moderating reflector. This concept has long been considered as a means of attaining very high temperatures in a gaseous core, since the fuel need not be in contact with structural material. A number of critical experiments have been performed on configurations of different core size and shape, with different structural material thicknesses between the cavity and reflector, with different coolant densities surrounding the core, and with various other alterations. The principal purpose was to evaluate the effects of engineering design variables for a cavity propulsion reactor concept. Experiments reveal that a power reactor with the required structure and a cavity size 182.9 cm (6 ft) in diameter by 121.9 cm (4 ft) long can be expected to have a critical core loading of between 20 and 30 kg of 235U.