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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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General Kenneth Nichols and the Manhattan Project
Nichols
The Oak Ridger has published the latest in a series of articles about General Kenneth D. Nichols, the Manhattan Project, and the 1954 Atomic Energy Act. The series has been produced by Nichols’ grandniece Barbara Rogers Scollin and Oak Ridge (Tenn.) city historian David Ray Smith. Gen. Nichols (1907–2000) was the district engineer for the Manhattan Engineer District during the Manhattan Project.
As Smith and Scollin explain, Nichols “had supervision of the research and development connected with, and the design, construction, and operation of, all plants required to produce plutonium-239 and uranium-235, including the construction of the towns of Oak Ridge, Tennessee, and Richland, Washington. The responsibility of his position was massive as he oversaw a workforce of both military and civilian personnel of approximately 125,000; his Oak Ridge office became the center of the wartime atomic energy’s activities.”
Technical Session|Panel|Sponsored by FCWMD
Monday, November 16, 2020|1:00–3:10PM EST
Session Chair:
Kaushik Banerjee
Session Organizer:
Alternate Chair:
Christina Leggett
Staff Producer:
Eileen Cullen (American Nuclear Society)
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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