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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
A. L. Pitner
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 77-85
Technical Paper | Material | doi.org/10.13182/NT76-A31626
Articles are hosted by Taylor and Francis Online.
Eighteen boron carbide specimens were irradiated for 355 effective full-power days in the Experimental Breeder Reactor II to maximum burnups of 82 x 1020 capture /cm3. Baseline specimens were patterned after Fast Flux Test Facility reference boron carbide, and material variables of 10B enrichment, pellet density, grain size, and stoichiometry were investigated in the test. Irradiation temperatures ranged from 1175 to 1570°F (635 to 855°C). Each specimen was individually instrumented to measure temperature and helium release continuously during irradiation.Postirradiation examination provided information on pellet integrity, swelling, tritium retention, and compatibility with stainless-steel containment components.
