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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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.