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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
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.
Donald M. Wiberg, Jan S. Woyski
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 35-45
Technical Paper and Note | doi.org/10.13182/NT68-A27983
Articles are hosted by Taylor and Francis Online.
Analog computer and theoretical results are presented to show the nonlinear stability of any steady-state propellant temperature and flow in a typical nuclear rocket engine. This assurance of stability encourages design of schemes in which the neutronics are not closely controlled, e.g., schemes involving only propellant flow control or on-off drum controllers. A detailed analog computer model was assembled and checked against experimental data. Step-by-step approximations were made to simplify the nuclear engine dynamic behavior. This process continued until a small number of equations were found that adequately described this behavior and were amenable to theoretical analysis. For locked control behavior described by simplified theoretical equations, very large transients are proven to be stable. For the general theoretical case, only preliminary results are now available, but computer results indicate equally stable behavior.