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The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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.”
Nuclear Technology | Volume 93 | Number 1 | January 1991 | Pages 53-64
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34518
Articles are hosted by Taylor and Francis Online.
A postulated loss-of-residual heat removal (RHR) event for a reactor coolant system (RCS) in a midloop condition is analyzed for the Palo Verde Nuclear Generating Station (PVNGS) using the RETRAN-2/MOD4 computer code. The PVNGS is a Combustion Engineering, two-loop, 3800-MW(thermal) pressurized water reactor (PWR). This analysis was prompted by the U.S. Nuclear Regulatory Commission generic letter 88-17, which requires PWR licensees to perform analyses of loss-of-RHR events for their facilities. Such analyses yield a detailed understanding of loss-of-RHR events and provide a basis for emergency procedures and recovery actions. Simulations of events following a loss of RHR are used to determine the time for RCS coolant to reach boiling, evaluate the potential for a rapid core uncovery due to pressurization of the reactor ves sel head with a corresponding liquid ejection from a cold-leg breach, and evaluate options for maintaining the RCS inventory above the core. Key features of the PVNGS midloop condition RETRAN model include isolating both steam generators from the RCS by nozzle dams, setting the initial RCS inventory at midloop, venting the RCS to containment by removing the pressurizer safety relief valves, defining a maintenance breach on one cold leg, and providing options to evaluate makeup water injection to a hot or cold leg by either pump or gravity feed. The RETRAN model provides a satisfactory method for dynamically evaluating loss-of-RHR events from a reduced RCS inventory condition, and for evaluating alternative recovery actions for PVNGS.