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. Brandes, H. Daoud, U. Schmid, V. Drüke
Nuclear Science and Engineering | Volume 97 | Number 2 | October 1987 | Pages 89-95
Technical Paper | doi.org/10.13182/NSE87-A27457
Articles are hosted by Taylor and Francis Online.
The pebble-bed prototype thorium high-temperature reactor represents the second step of high-temperature gas-cooled reactor development in the Federal Republic of Germany. Nuclear commissioning of the plant began in August 1983 with the loading of the spherical elements, and first criti-cality was achieved in September 1983 with the loading of 198 180 spherical elements. A very good agreement of 0.004Δk was achieved between measured and calculated values. After full loading of the core with 674200 elements in October 1983, core physics tests were performed in air and nitrogen in August 1984 to verify the design calculations. In these tests the temperature coefficient, the control rod worths, and the reactivity of the reactor core were measured. The measured values of the temperature coefficient were within 10% of the expected values. The agreement between measured and expected control rod worths (5%) is excellent. The reactivity of the cold core with all rods withdrawn was determined to be 0.112 ± 0.005Δp. Taking into account values of the packing density of the spherical elements, which were higher than expected, the calculated value of 0.11Δp was in very good agreement.