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.
S. H. Jiang, H. Werle
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 354-362
Technical Paper | doi.org/10.13182/NSE78-A27218
Articles are hosted by Taylor and Francis Online.
The 252Cf fission neutron-induced gamma fields in iron have been investigated experimentally and theoretically. The gamma leakage spectra from a series of relatively small iron spheres (15 to 35 cm in diameter) and the space-dependent gamma spectra within a relatively large (∼100- × 100- × 100-cm) steel pile have been measured with an absolutely calibrated Si(Li). Compton spectrometer in the energy range from 0.3 to 3 MeV. In addition, neutron spectra (with a spherical proton recoil proportional counter and a 3He semiconductor spectrometer) and 235U fission rates have been measured within the steel pile. The measurements are compared with calculations. For the calculation of the neutron spectra, we used the one-dimensional neutron transport code DTK (208 energy groups), and for the calculation of the gamma spectra, an extended version (51 energy groups) of the gamma transport code BIGGI 4T and an (n-γ) production cross-section matrix constructed from published data were used. The gamma flux induced by inelastic neutron scattering is well reproduced by the calculations, whereas that induced by capture processes is somewhat underestimated (∼20%).