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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
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.”
Hugues W. Bonin, Ian Miedema, Van Tam Bui
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 286-304
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4027
Articles are hosted by Taylor and Francis Online.
In Canada, the spent nuclear fuel disposal method proposed is to permanently isolate the spent fuel in deep underground vaults carved in stable granite rock formations within the Canadian Shield, with the integrity of the isolation to be assured for a minimum period of 500 yr. The present work aims at determining the feasibility of using a consolidated composite material made of an advanced polymer called PEEK (Poly Ether Ether Ketone) and continuous graphite fiber to fabricate a container designed to isolate the spent nuclear fuel from the biosphere for such very long time periods. The research focused on submitting the PEEK-based composite material to a thermal and radioactive environment comparable to, and, in some aspects, more aggressive than, the conditions of exposure in the disposal vault. The changes to the physical, mechanical, and chemical properties of the material following prolonged exposure were then determined. The simulation of the environment was achieved by irradiating numerous test specimens in a mixed radiation field produced by a SLOWPOKE-2 nuclear research reactor at controlled ambient temperatures ranging from ~20 to 75°C. The specimens were characterized via several methods: tensile and flexural testing, differential scanning calorimetry, scanning electron microscopy, and wide-angle X-ray scattering. The results confirmed that the PEEK-based composite material was resistant to exposure to high radiation doses (1 MGy), at temperatures between ~20 and 75°C. The mechanical and other properties were barely affected, with values rarely exceeding 1 of the properties of nonirradiated samples, suggesting that the PEEK-graphite fiber composite material can indeed be considered as a very good candidate for this demanding application.