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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.
C. F. Bullinger, W. J. Kann
Nuclear Science and Engineering | Volume 3 | Number 4 | April 1958 | Pages 379-386
Technical Paper | doi.org/10.13182/NSE58-A25475
Articles are hosted by Taylor and Francis Online.
The control rod drive mechanisms installed on the Argonne Experimental Boiling Water Reactor (EBWR) are of an externally operated lead screw and nut type in which the control rod extension shafts are driven through pressure breakdown, collected leakage seals. The mechanisms which are located below the reactor are fabricated from conventional industrial materials, such as carbon steel, brass, cast iron, nylon, etc., and are lubricated with grease. They may be serviced during reactor operation, and are removable from the reactor without the necessity of draining the reactor vessel. This feature has proven to be worthwhile in operation. The mechanism is adaptable to reactors operating at pressures up to 1500 psi and requiring up to a 6-foot control rod stroke. This paper describes the development of the mechanism, the final design and proof-testing program, and some of the particular design difficulties encountered. Some of the other drive types, including electromagnetic jack, hydraulic, and rotary seal rack-and-pinion, considered for EBWR application, are also discussed.