ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Winter Conference & Expo
November 15–18, 2026
Phoenix, AZ|Arizona Grand Resort & Spa
Latest Magazine Issues
Sep 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
Fusion Science and Technology
Latest News
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.
Karl O. Ott, Robert C. Borg
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 243-261
Technical Paper | doi.org/10.13182/NSE77-A26960
Articles are hosted by Taylor and Francis Online.
An in-depth discussion of the problems of the current description of the growth rate (or doubling time) of breeder reactor fuel emphasizes the need for conceptually improved computational procedures. The presented derivation of improved measures for the growth of breeder reactor fuel is based on a formally correct description of the fast reactor fuel cycle. From these derivations one obtains a hierarchy of four logically different expressions for the fuel growth rate, which yield formally the same value. The first (and most general) definition is obtained by mathematically expressing the doubling time as a measure of the asymptotically exponential growth of fuel in a system of identical breeder reactors. The second definition represents the condensation of the detailed information of the equilibrium fuel cycle analysis for a single reactor. The third growth rate expression is also based on the detailed fuel cycle analysis. Coefficients of an“integrated fuel cycle model” are obtained from the detailed information. This leads to an eigenvalue problem with the growth rate as eigenvalue and the equilibrium plutonium composition as eigenvector. The fourth growth rate expression is based on a set of isotopic weight factors, which is obtained as solution of the adjoint of the fuel cycle eigenvalue problem employed in the third procedure. The resulting “breeding worth factors” are applied to the production and consumption rates of the four plutonium isotopes. This makes the resulting doubling time formula stationary with respect to variations about a reference reactor and practically independent of the fuel composition.