ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.
Thomas F. Plunkett
Nuclear Technology | Volume 3 | Number 3 | March 1967 | Pages 178-186
Technical Paper and Note | doi.org/10.13182/NT67-A27872
Articles are hosted by Taylor and Francis Online.
The gaseous-core or cavity nuclear reactor is of significant interest for advanced nuclear propulsion because of its high performance capabilities compared to solid-core nuclear and chemical propulsion concepts. By removal of temperature limitations associated with solid materials in the core and by use of radiative transfer as the principal mode of energy transfer from the fuel to the propellant, propellant exhaust temperatures of 7000°K and specific impulses in excess of 2000 sec can be obtained. This article describes a detailed nuclear analysis of a gaseous-core nuclear rocket engine in which the spatial effects of the cavity liner material, coolant tubes, and structural components, as well as neutron streaming out of propellant inlet and outlet (nozzle) passages, are considered. Calculational methods were evaluated, and multigroup diffusion theory was selected. Two-dimensional diffusion and transport calculations are compared for finite cylindrical cavity reactors having both central and annular nozzle exhausts. A parameter study was made of fuel and reflector materials, core and reflector dimensions, and temperature effects. Significant results of this study are: 1) extremely high fuel loadings are required for a propulsion reactor; 2) substantial preheating of the reflector will be required for startup; and 3) uranium-233 has significant advantages over 235U and 239Pu as fuel in gaseous-core nuclear rockets.