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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.
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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
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.”
Luis E. Herranz, José I. Linares, Beatriz Y. Moratilla
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 15-24
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3853
Articles are hosted by Taylor and Francis Online.
Future world energy demand will require a sustainable energy generation system. Optimization of power cycles has become a key element to better exploit natural resources, to minimize waste production, and even to reduce fuel cycle cost. Aware of this, nuclear technology is developing what has been termed Generation IV designs. In particular, the high-temperature gas-cooled reactor (HTGR) concept is a promising technology to reach much higher thermal efficiencies than present nuclear power plants.By using a classical thermodynamic methodology, this paper demonstrates that regenerative reheating would significantly enhance the thermal performance of a reference Brayton cycle based on pebble bed modular reactor (PBMR) technology. The regenerative reheating is conducted by a live gas fraction () extracted from the coolant inventory exiting the nuclear reactor. Optimization of results in efficiency values as high as 53 and 61%, respectively, under current and midterm technology scenarios. In addition, reheating would allow an effective and easy-to-conduct "load-follow" operation with no loss of thermal efficiency in the upper range of . Even further, under the midterm technology scenario, reheating would make it possible to cogenerate H2 from the enthalpy content of the fraction exiting reheater.