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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.
Guy H. Cannon
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 219-224
Technical Paper | doi.org/10.13182/NSE59-A25587
Articles are hosted by Taylor and Francis Online.
Heat output of a nuclear reactor is independent of temperature and is limited only by the rate at which heat can be removed from the system. Means are suggested for improving the heat removal capability of a reactor by redistributing the fuel, shaping the heat-transfer surface, and directing the flow of coolant in a manner such as to cause all of the increased heat-transfer surface to operate at the highest permissible temperature and thereby maximize the temperature difference applicable for heat-transfer. With “Calder Hall” as a reference and employing the same materials of construction and proportions (fuel, cladding, moderator, coolant), and using the same operating conditions (coolant pressure, coolant pumping power, maximum cladding temperature), this paper suggests ways of fabricating equivalent magnesium-clad wedge S-shape fuel plates and using them in clumps for heating more coolant to higher temperature. The indicated result is greatly increased power production because of increased coolant throughput at increased outlet temperature and improved thermal efficiency.