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Westinghouse, Nordion, and PSEG team up to produce Co‑60 in the United States
This past January, Westinghouse Electric Company, Nordion, and PSEG Nuclear formalized agreements to implement newly developed cobalt-60 production technology at Units 1 and 2 of PSEG’s Salem nuclear power plant in New Jersey, with the Co-60 to be supplied to Nordion. Through an ongoing joint initiative, the companies aim to harness U.S. pressurized water reactors to produce a key medical isotope and build the first commercial-scale Co-60 production platform in the United States.
D. A. Niebruegge, E. L. Tolman, C. W. Solbrig
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 363-368
Technical Note | doi.org/10.13182/NSE78-A27316
Articles are hosted by Taylor and Francis Online.
Thus far, existing computer programs have been adequate to predict the behavior of the loss-of-fluid test facility (LOFT) non-nuclear loss-of-coolant experiments. The work presented here describes a predictive capability for modeling nuclear experiments to determine if the same fuel can be used in several experiments. This is analogous to determining if fuel may be reused after a pressurized water reactor loss-of-coolant accident. We are concerned here with discussing only best-estimate calculations for experimental predictions and not the conservative models used for licensing. It was found that an adequate analysis procedure could be established by modeling accurately the fuel stored energy before the experiment is initiated. The initial stored energy in the fuel was found to be the most important fuel rod parameter influencing the maximum cladding temperature obtained in the transient.