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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
Argonne updates: Fuel research and materials lab
Over the past two weeks, Argonne National Laboratory has announced numerous significant advancements being made by its staff to push forward nuclear fuels and materials research. Those announcements include the opening of the new Activated Materials Lab, the development of a new measurement technique, and the application of new artificial intelligence tools.
J. D. Cerchione, W. R. Wallin, R. E. Rice
Nuclear Technology | Volume 2 | Number 1 | February 1966 | Pages 11-20
Technical Paper | doi.org/10.13182/NT66-A27561
Articles are hosted by Taylor and Francis Online.
BORAX-V was the fifth in a series of boiling-water reactors operated by Argonne National Laboratory at the National Reactor Testing Station in Idaho. It was the first integral boiling-water nuclear superheating reactor to be operated in the United States. Super-heated steam was produced, in different experiments, in both the central and peripheral regions of the core. The nominal design maximum power of 20 MW(th) and 850°F exit steam temperature were both exceeded. Operational procedures and results of experiments are discussed. Areas of particular interest and investigation include the following: comparison of a centrally versus a peripherally located superheater core; superheater startup and shutdown cooling problems; superheater flooding reactivity worth and inadvertent flooding hazard; control of power split between the boiler and superheater zones of the reactor core; superheater fuel-cladding-material integrity; plant radioactivity levels; results of operation with defective fuel in both the boiler and superheater areas of the core; in-core instrumentation and data collection; transfer-function and physics experiments; and the water-chemistry program.