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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
2020 ANS Virtual Winter Meeting
November 16–19, 2020
Virtual Meeting|Online
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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Oct 2020
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Nuclear Science and Engineering
November 2020
Nuclear Technology
October 2020
Fusion Science and Technology
August 2020
Latest News
Nuclear Science Week: the ANS local and student sections events
Nuclear Science Week (NSW) is a celebration designed to focus local, regional, national, and international interest on all aspects of nuclear science. National events marking the 11th annual NSW took place October 19–23 in Washington, D.C. This year’s theme was “Think Clean. Think Solutions. Think Nuclear.”
Several ANS local and student sections from around the world organized their own events to celebrate NSW, as follows:
Technical Session|Sponsored by RPD
Thursday, June 11, 2020|9:00–10:45AM (10:00–11:45AM EDT)
Session Chair:
Jason Hearne (LANL)
Alternate Chair:
Pavel Tsvetkov (LANL)
Session Organizer:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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A Unified Form of Stabilized Finite Element Methods for Solving the First-order Neutron Transport Equation
Liangzhi Cao (Xi’an Jiaotong Univ.), Chao Fang (Xi’an Jiaotong Univ.), Hongchun Wu (Xi’an Jiaotong Univ.)
Summary
Relaxation of Quasi-Static Approach via Polynomial Interpolation in the Predictor Corrector Quasi-Static Method
T. Oh (KAIST), Yonghee Kim (KAIST)
Unstructured Mesh-Grid Multi-Physics Analysis with Monte Carlo iMC Code for Advanced Fuel Elements
Hyeontae Kim (KAIST), Yonghee Kim (KAIST)
Conceptual Safety Design Report for the Versatile Test Reactor
Doug Gerstner (INL), Jason Andrus (INL), Troy Reiss (INL)
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