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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Proposed rule for more flexible licensing under Part 53 is open for comment
The Nuclear Regulatory Commission has published a proposed rule that has been almost five years in the making: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors. The rule, which by law must take its final form before the end of 2027, would let the NRC and license applicants use technology-inclusive approaches and risk-informed, performance-based techniques to effectively license any nuclear technology. This is a departure from two licensing options with light water reactor–specific regulatory requirements that applicants can already choose.
Thierry Cadiou, Jacky Louvet
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 256-263
Technical Paper | Sodium Technology - Reactor Safety | doi.org/10.13182/NT06-A3705
Articles are hosted by Taylor and Francis Online.
Upon request of the French Safety Authorities, the transient phase, initiated by a total instantaneous blockage (TIB) in a Phénix reactor fuel assembly, has been investigated. Based on an experimental program performed with the SCARABEE reactor, the phenomenology of the accident is first presented. The SIMMER code, which models fast reactor core disruptive accidents, is then used to analyze the transient phase in order to establish the chronology of the events occurring in the faulty assembly after its blockage. This study concludes that the time between the TIB and the onset of structure melting in the neighboring assemblies is sufficient to scram the reactor by control rod insertion before propagation of the accident to the rest of the core.