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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.
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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.”
P. Y. Hsu, L. G. Miller, G. A. Deis, Y. D. Harker, G. R. Longhurst, T. S. Born, E. H. Ottewitte, K. D. Watts
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1216-1221
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A23023
Articles are hosted by Taylor and Francis Online.
A large-volume, distributed, pulsed, 14 MeV neutron source, which utilizes the high powered (270-GW) Power Burst Facility (PBF) at the Idaho National Engineering Laboratory, is described. The concept of utilizing existing fission test reactors to test fusion first wall/blanket (FW/B) components and systems has been adequately documented. In all previous scenarios, the normal fission spectrum (including tailoring) was shown to produce adequate heating profiles and some tritium breeding. However, one recognized shortcoming has been the absence of the 14 MeV neutron component. This paper describes a scheme whereby the fission neutrons would be employed to produce the desired 14 MeV component. The data obtained from tests in this large-volume [20 em (8 in.) in diameter and 90 em (36 in.) in length], distributed neutron source will pertain to both near-term (Tokamak Fusion Test Reactor—TFTR) and future pulsed fusion machines. Specifically, application requiring high flux but low fluence is foreseen in the areas of dosimetry benchmarking for tritium breeding performance code verification. As a general purpose, FW/B integrated technology development capability, the PBF is shown to be pertinent to addressing the bulk-heated, solid breeder blanket thermal and mechanical issues; tritium permeation in the presence of radiation, and barrier development in the prototypical radiation environment associated with the first wall; issues associated with the technology of breeder materials; and in situ tritium recovery process characterization and system development.