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
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.
Joseph J. Prabulos, Jr, Alexander Sesonske
Nuclear Technology | Volume 3 | Number 5 | May 1967 | Pages 275-282
Technical Paper and Note | doi.org/10.13182/NT67-A27885
Articles are hosted by Taylor and Francis Online.
An evaluation is made of variations in reactor physics and engineering parameters during the core lifetime (100 000 MWd/mt) for a large 1000-MW(e) fast-thermal coupled reactor containing oxide fuel material. The analysis includes a comparison between the thorium and plutonium breeding cycles, as well as an estimate of the effects of several types of fuel management on reactor design variables. While the analysis indicates poor breeding characteristics for the particular design considered, the calculational methods developed and the relative parametric trends computed are of more general applicability.