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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.
W. R. Gambill, R. D. Bundy
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 69-79
Technical Paper | doi.org/10.13182/NSE64-A18141
Articles are hosted by Taylor and Francis Online.
In support of the High Flux Isotope Reactor Program, experimental determinations were made of friction factors, burnout heat fluxes, and average and local nonboiling heat-transfer coefficients for forced-convection flow of water through thin aluminum and nickel rectangular channels under the following conditions: heat flux = 0.1 × 106 to 7.4 × 106 Btu/h·ft2, velocity = 10 to 85 ft/sec, Reynolds number = 9,000 to 270,000, pressure = 1 to 39 atmospheres absolute, flow gap = 0.043 to 0.057 in., and heated length = 12 and 18 in. A few tests were made to ascertain the effect of an axially oriented cylindrical spacer strip on surface-temperature distribution and burnout heat flux. The results of these studies, unlike those of some earlier investigations of narrow-gap heat transfer, are in reasonably good agreement with accepted correlations. The friction factors are in satisfactory agreement with the Moody chart for the relative roughness of the test sections used, the burnout heat fluxes are well reproduced by the Soviet Zenkevich-Subbotin correlation, and the local and average heat-transfer coefficients are slightly larger than values predicted by the Hausen and Sieder-Tate equations.