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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jul 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
August 2026
Fusion Science and Technology
Latest News
$40M investment to spur new nuclear developments in Idaho and Wyoming
On Monday, the U.S. Department of Commerce announced that its Economic Development Administration (EDA) intends to award $31 million to the Intermountain-West Nuclear Energy Corridor (INEC) Tech Hub. The Idaho Advanced Energy Consortium (IAEC), the group that leads the INEC Tech Hub, subsequently announced that matching donations from its stakeholder partners will bring the total investment up to $40 million.
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.