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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.
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Corinne Bangil, Gérard Gambier, Michel Soldevila
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 344-349
Technical Paper | Probabilistic Safety Assessment and Risk Management / Fuel Cycle | doi.org/10.13182/NT89-A34218
Articles are hosted by Taylor and Francis Online.
Pressurized water reactor four-batch fuel management represents, in the present context, an economic optimum for the French standardized series of reactors. Plutonium recycling on an industrial scale has already started in France; therefore, it is essential to ascertain its compatibility with four-batch refueling requirements. In the survey considered, it is shown that a core refueled annually with 28 UO2 assemblies, having a 3.7% 235 U content and 12 mixed-oxide assemblies containing 6.5% plutonium, entirely satisfies safety criteria under normal operating conditions. A supplementary survey will be performed to assess its behavior under such accident conditions as steam line break and rod ejection.