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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Oct 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
October 2024
Latest News
Westinghouse reorganization creates two new business units
Westinghouse Electric Company has announced that it will create two new global business units from its Operating Plant Services business. Effective January 1, 2025, the new units will be Long-Term Operations and Outage & Maintenance Services.
Robert V. Strain, Kenny C. Gross, John D. B. Lambert, Richard P. Colburn, Toshihiro Odo
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 227-240
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34618
Articles are hosted by Taylor and Francis Online.
A test containing 19 mixed-oxide fuel pins was operated in the Experimental Breeder Reactor II (EBRII) at peak cladding temperatures near 800°C. Two test pins that had been designed to fail at ∼5 at. % burnup and two low-burnup environmental pins failed and then were operated in the run beyond cladding breach mode for 22 days. Very high delayed neutron signals occurred during the irradiation of the test, and it was terminated as a result of high delayed neutron signals and evidence of plutonium in the coolant. Each of the four pins exhibited multiple breaches in the upper half of the fuel column. Measurements of fuel trapped on the filter section of a deposition sampler that was located above the test indicated that ∼2.7 g of fuel was lost during the irradiation. Postirradiation examination of the pins indicates that most of the fuel was lost from a single pin. The fuel loss resulted in an increase in the background delayed neutron signal but had no other deleterious long-term effect on the operation of the EBR-II.