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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.”
Jorge Gonzalez-Amoros, Marianna Papadionysiou, Seongchan Kim, Han Gyu Joo
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1634-1655
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2140577
Articles are hosted by Taylor and Francis Online.
The capability of the ESCOT pin-level nuclear reactor core thermal-hydraulic (T/H) code is extended for the multiphysics analysis of hexagonal geometry cores, and its performance is assessed by a code-to-code comparison with COBRA-TF (CTF). ESCOT is an accurate yet fast core T/H solution aimed at high-fidelity and high-resolution multiphysics core analysis in the framework of massively parallel computing platforms. The coupling of ESCOT with the nTRACER direct whole-core calculation code is enhanced for the hexagonal geometry handling needed for VVER core analysis. The lateral momentum terms, the turbulent mixing coefficient values, and the parallelization algorithms are modified to handle hexagonal geometry. The newly implemented ESCOT features are verified by comparing single-assembly and full-core steady-state standalone and coupled solutions for the VVER-1000 benchmark X-2 with CTF results.
The ESCOT and CTF results show differences within an acceptable range in both standalone and coupled calculations. The computing time superiority due to the use of the drift flux model (DFM) of ESCOT over the CTF two-fluid model is corroborated with a speedup factor of 1.5. The use of the DFM together with the axial-radial parallelization capability of ESCOT makes ESCOT an ideal alternative to replace the simplified built-in T/H solver in nTRACER as the coupled simulation results demonstrate.