ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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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Apr 2024
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Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Zap Energy hits 37-million-degree electron temperatures in compact fusion device
Zap Energy announced April 23 that it has reached 1-3 keV plasma electron temperatures—roughly the equivalent of 11 to 37 million degrees Celsius—using its sheared-flow-stabilized Z-pinch approach to fusion. Reaching temperatures above that of the sun’s core (which is 10 million degrees Celsius temperature) is just one hurdle required before any fusion confinement concept can realistically pursue net gain and fusion energy.
International High-Level Radioactive Waste Management Conference
Workshop
Sunday, November 13, 2022|9:00AM–12:00PM MST|Honeysuckle
UNF-ST&DARDS is being developed to provide the ability to perform automated analysis of spent nuclear fuel (SNF) storage, transportation, and disposal systems. UNF-ST&DARDS provides a database for storing and preserving SNF data and streamlines various analyses using the data from the database for time-dependent characterization of SNF and related systems (e.g., dry storage system). UNF-ST&DARDS allows for modelling the variation of cask payload burnup, enrichments, and cooling times through a flexible GUI. This tutorial will include 1) discussions on various data need for realistic SNF characterizations and demonstration of the data import processes in UNF-ST&DARDS, 2) assembly-specific, time-dependent depletion and decay analyses, 3) as-loaded (using actual cask loading maps) criticality and shielding analyses of currently loaded casks for storage, transportation, and disposal (over disposal time periods), 4) discussion of as-loaded analyses to support licensing/certification of dry SNF systems, 5) misload analysis methodology to support as-loaded criticality analysis, 6) design-basis criticality and shielding analyses using user-defined loading patterns and fuel assembly types, and 7) dry storage loading optimization using UNF-ST&DARDS. The tutorial/demonstration is open to all registered meeting attendees who signed up at the time of registration. Attendees have no requirements to watch the demonstration, however, an RSICC license for UNF-ST&DARDS and SCALE is necessary if they would like to follow along.
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