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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Nuclear Science and Engineering
April 2024
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February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Technical Session|Sponsored by RPD
Thursday, June 11, 2020|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.)
Paper
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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