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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Selim Sancaktar, T. van de Venne
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 112-117
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34447
Articles are hosted by Taylor and Francis Online.
Insights obtained from various probabilistic risk analysis (PRA) studies performed by the Westinghouse Electric Corporation and associates on new pressurized water reactor (PWR) designs are briefly discussed and compared. The discussion is limited to internal initiating events since external event analysis requires site-specific data. The plant core melt frequency resulting from these initiating events is used as the measure to identify dominant accident sequences. The initiating events, failures of frontline safety systems and their support systems, operator actions, and consequential failures are used to measure the response of each design to various safety issues discussed. A conventional PWR plant is used as the base to compare the features of the different designs and the insights obtained from the PRA studies. The cases discussed include (a) a conventional PWR plant design (Westinghouse), (b) a Progetto Unificato Nucleare design (Westinghouse and Ansaldo), (c) a Sizewell-B design (Westinghouse and National Nuclear Corporation), and (d) an advanced PWR design (Westinghouse and Mitsubishi Heavy Industries). In studies (b), (c), and (d), PRAs are performed in the early design stages to evaluate the effect of primary safety and support systems on the plant core melt frequency. The results of the PRA evaluations are used, together with other considerations, to make appropriate design modifications. The experience obtained from studies (b), (c), and (d) leads to the conclusion that PRAs are effective in supporting early plant design efforts for engineered safety systems. Probabilistic risk analysis models provide an additional decision-making tool to evaluate the importance and effect of various design alternatives.