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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.”
Gennadi Manturov
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE03-A2354
Articles are hosted by Taylor and Francis Online.
The data-processing system CONSYST/ABBN coupled with the ABBN-93 nuclear data library (NDL) was used in the analysis of BFS-62 and ZPPR JUPITER experiment series fast reactor mixed oxide cores, applying the Japan Nuclear Cycle Development Institute (JNC), Japan, core calculation code CITATION-FBR. The FFCP cell code was used to take into account the spatial cell heterogeneity and resonance effects based on the subgroup approach.The NDL effect has been studied by comparing the results calculated using the ABBN-93 nuclear data with the former ones obtained at JNC based on the JENDL-3.2 NDL. Calculation analysis results for the keff parameter for four BFS-62 cores as well as for three ZPPR JUPITER experiment series cores (ZPPR-9, ZPPR-13A, and ZPPR-17A) have been obtained. The estimated uncertainty in the keff values caused by possible errors in calculation of the applied corrections was estimated to be ~0.3% in the case of the ZPPR cores and 0.2% for the BFS-62 cores. The NDL effect determined by applying the ABBN-93 nuclear data in the JNC calculation route for the keff parameter appeared to be ~0.3% for the ZPPR and BFS-62 cores with plutonium. As for BFS-62 uranium-loaded cores, the NDL effect was ~0.1%. Sensitivity analysis was applied, and it has shown that the main contributors to the NDL effect are uranium, plutonium, and iron cross sections.This work is closely related to the JNC-Institute of Physics and Power Engineering, Russian Federation, collaboration on experimental investigation of excess weapon plutonium disposition in the BN-600 reactor using the BFS facility.
