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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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August 2020
Latest News
Missouri S&T’s nuclear engineering program gains department status
Missouri S&T’s pool-type nuclear reactor. Photo: Sam O’Keefe/Missouri S&T
Sixty years ago, the Missouri University of Science and Technology (Missouri S&T), then known as the University of Missouri at Rolla, was one of the first U.S. institutions to offer a nuclear engineering degree. Now, decades after it was offered as an option within metallurgical engineering, Missouri S&T’s nuclear program has attained new status as the Nuclear Engineering and Radiation Science Department, the university announced on October 20.
Technical Session|Panel|Sponsored by FCWMD
Monday, November 16, 2020|12:00–2:10PM (1:00–3:10PM EST)
The session will be available to join at 11:30AM (12:30PM EST).
Session Chair:
Kaushik Banerjee
Session Organizer:
Alternate Chair:
Christina Leggett
Spent nuclear fuel (SNF) cask systems are evaluated for approved contents that provide bounding fuel characteristics (design-basis) such as fuel type, initial enrichment, and discharge burnup. The bounding fuel characteristics establish the upper limits of the cask's safety parameters (e.g., dose rates). Due to the wide variation in SNF assembly burnup values and discharge dates, cask systems are loaded with assemblies that satisfy the bounding fuel characteristics with some amount of uncredited safety margin. In this session, we will discuss (1) design-basis and as-loaded analysis approaches and (2) various applications of uncredited safety margins that can be quantified by as-loaded analyses. The as-loaded analysis approach has the potential to significantly improve SNF management and streamline the regulatory review process.
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