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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Steven A. Wright, Erhard A. Fischer, Peter K. Mast, Gustav Schumacher
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 326-340
Technical Paper | Analyse | doi.org/10.13182/NT85-A33730
Articles are hosted by Taylor and Francis Online.
During an unprotected loss-of-flow accident in a liquid-metal fast breeder reactor, the mode of fuel disruption in sodium-voided channels and the subsequent fuel and clad motion are important issues that determine the further accident sequence. To study these phenomena, a series of in-pile fuel disruption experiments, FD2/4, were performed, and the fuel behavior was recorded by high-speed cinematography. Power transients typical of a heterogeneous (e.g., Clinch River Breeder Reactor) and a homogeneous (e.g., SNR-300, Federal Republic of Germany) core design were employed. In the first case, large-scale liquid swelling was observed, whereas in the second case, disruption by solid-state breakup occurred. Both observations provided direct experimental confirmation of the assumption usually made in the accident analysis, and thus removed still existing modeling uncertainties concerning the disruption behavior.