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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
June 2024
Nuclear Technology
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Latest News
ANS Standards Committee publishes joint ASME/ANS standard for Level 1/large early release frequency PRA
ANSI/ASME/ANS RA-S-1.1-2024, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, has been published by the American Nuclear Society. The document, which is a joint standard developed with the American Society of Mechanical Engineers by the ANS/ASME Joint Committee on Nuclear Risk Management, received the approval of the American National Standards Institute on February 29, 2024, and was issued on March 15, 2024.
Jacob Keese, D. Keith Hollingsworth
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 165-179
Research Article | doi.org/10.1080/00295450.2023.2216989
Articles are hosted by Taylor and Francis Online.
A more advanced form of nuclear propulsion known as centrifugal nuclear thermal propulsion (CNTP) promises increased propellant temperatures that could lead to a high specific impulse in the range of 1500 to 1800 s with hydrogen. This design has the potential of opening opportunities to perform missions to destinations much farther than currently possible. However, the CNTP concept poses many engineering challenges due to the nuclear fuel operating at high temperature in a liquid phase. A one-dimensional, steady-state thermal model of the liquid uranium fuel has been constructed to understand the limitations of this concept and the potential design considerations. Three related basic designs are considered, and key design parameters are varied in order to predict the temperature levels and void fractions across the liquid uranium pool.