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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.”
Jean Boscary, Masanori Araki, Satoshi Suzuki, Koichiro Ezato, Masato Akiba
Fusion Science and Technology | Volume 35 | Number 3 | May 1999 | Pages 289-296
Technical Paper | doi.org/10.13182/FST99-A82
Articles are hosted by Taylor and Francis Online.
The purpose of the International Thermonuclear Experimental Reactor (ITER) divertor, which is located at the bottom of the vacuum vessel, is to exhaust impurities and their power from the plasma. Divertor plates function to withstand and to remove a steady-state surface heat flux of 5 MW/m2 and a transient peak heat flux up to 20 MW/m2 for 10 s on the side that faces the plasma. These demanding heat loads require active cooling by a pressurized subcooled flow of water as well as the development of a high-performance cooling channel to avoid burnout. Previous experiments showed that a screw tube, which is a tube whose inner surface is machined like a nut, is an efficient means of removing high heat fluxes. New experiments have been carried out with a B 0205 M10 type of screw copper tube. The average inner diameter, i.e., at the midheight of the fin, is 10 mm, and the outer diameter is 14 mm. Different pitches have been investigated: 1.5, 1.25, 1, and 0.75 mm. Incident critical heat fluxes (ICHFs) between 25 and 47 MW/m2 have been reached for local pressures ranging from 0.9 to 2.2 MPa, inlet temperatures from 17 to 33°C, and axial velocities from 3.6 to 14 m/s. ICHF increases as axial velocity increases and depends slightly on local pressure. Experimental results confirm the potentialities of the screw tube as a reliable geometry for fusion cooling tubes.