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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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!
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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
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.