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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.
David Blanchet, Bruno Fontaine
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 260-274
Technical Paper | doi.org/10.13182/NSE13-59
Articles are hosted by Taylor and Francis Online.
The current design studies on sodium-cooled fast reactors (SFRs) are breaking with the past since they are guided by a new set of design criteria arising from the objectives of Generation IV reactors. The new safety requirements lead to designing reactors with breakeven breeding cores because in terms of reactivity control, they minimize the need to limit the consequences of an inadvertent control rod withdrawal event. Furthermore, as the reactivity control needs are low, a breakeven core enables the use of absorbing materials with reduced efficiency (natural boron, hafnium, etc.), which may be less costly than enriched boron. However, control rods designed with low absorbing materials may present the disadvantage of a nonnegligible loss of efficiency due to their consumption under irradiation. This paper presents a methodology to accurately calculate and to analyze the impact of this consumption on reactivity control.