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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Emmanuelle Picard, Jean Noirot, Raymond L. Moss, Helmut Plitz, Karl Richter, Jacques Rouault
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-2
Articles are hosted by Taylor and Francis Online.
An experimental program focused not only on the study of high-plutonium-content mixed-oxide fuels but also on more advanced "Pu without U" fuel concepts has been launched in the framework of the Consommation Accrue de Plutonium dans les RApides (CAPRA) project. First results of the in-pile and out-of-pile behavior of high-plutonium-content fuels with uranium, such as (U55%,Pu45%)O2, and (U55%,Pu40%,Np5%)O2, and also without uranium, such as (Pu44%,Ce56%)O2, are now available. In particular, the Irradiation à FOrt Pu (IFOP) experiment in the SILOE reactor and the TRAnsmutation and Burning of ActiNides in Triox carrier (TRABANT1) experiments in the High Flux Reactor are presented and the results are analyzed: Up to a burnup of 1.5 at.%, destructive examinations of the IFOP pin have shown that the high-plutonium-content oxide fuel with a large central hole presents the usual global behavior (good pellet integrity, fuel microstructure). The TRABANT1 oxide fuel pin with a 40% Pu and 5% Np content demonstrates that a burnup of 9.5 at.% can be reached without failure by a high-plutonium-content fuel. However, the TRABANT1 pin 1 (oxide pin with 45% Pu), which had run under severe conditions, has failed at ~7 at.% burnup. Destructive examinations of these pins will give more evidence on the causes of the failure. The low-oxygen-to-metal fuel column of (Pu,Ce)O2-x melted, thus confirming the poor conductivity of this fuel.
