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.
Gerald Klotzkin, Richard W. Swanson, Paul Hart, L. J. Harrison
Nuclear Science and Engineering | Volume 86 | Number 2 | February 1984 | Pages 206-218
Technical Paper | doi.org/10.13182/NSE84-2
Articles are hosted by Taylor and Francis Online.
Studies have been conducted at the Transient Reactor Test Facility (TREAT) to determine the variation during transient irradiation experiments of the ratio of axial midplane test fuel power to reactor power as measured by ex-core ion chamber current. It is shown that the dependence of this ratio on core temperature is generally small. However, effects due to control rod motion can be substantial. A simple mathematical expression that predicts the dependence of this ratio on control rod position is shown to give good agreement with integral experimental data. This work makes possible refinements in obtaining the desired power-versus-time behavior in test fuel by accounting for the effects of instantaneous position of control rods and core temperature during transient operation.