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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.”
Stefan Schmid, Rudi Kulenovic, Eckart Laurien (University of Stuttgart)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 406-413
For the investigations of leakage flow rates with reduced stagnation pressure (maximum 1.0 MPa) and stagnation temperature (maximum 170 °C) compared to real plant conditions, the Leakage Flow (LF) test rig is used. The design of the test rig enables experimental measurements of leakage flow rates through cracks with different shapes, sizes and wall thicknesses.
In the paper, experimental results of leakage flow measurements for one artificial through-wall crack geometry with a rectangular shape are presented. The fluid conditions of the investigations vary in the pressure range from 0.2 MPa to 1.0 MPa with a maximum temperature of 170 °C. The experimental values in the single-phase regime up to 90 °C are used to calculate the overall loss coefficient respectively the friction factor and are compared to theoretical models. The results at elevated temperature from 100 °C to 170 °C are discussed considering the subcooling of the fluid and compared to theoretical values calculated by the modified Bernoulli equation.