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.
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
DOE-EM awards $74.8M Oak Ridge support services contract
The Department of Energy’s Office of Environmental Management has awarded a five-year contract worth up to $74.8 million to Independent Strategic Management Solutions for professional support services at the Oak Ridge Office of Environmental Management site in Oak Ridge, Tenn.
L. S. Tong
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 7-15
Technical Paper | doi.org/10.13182/NSE68-A20912
Articles are hosted by Taylor and Francis Online.
Flow boiling crisis can be categorized into at least two types: Departure from Nucleate Boiling (DNB) in the subcooled and low-quality region and dry-out in the high-quality region. To analyze the DNB flux in a rod bundle, the flow conditions should be evaluated by a subchannel analysis and a single-channel DNB correlation can be used for predictions. Rod-bundle DNB data have been presented to verify the above statement. The uncertainties in the measured DNB heat fluxes are listed as: statistical nature of flow turbulences and surface conditions, ±3%; fabrication tolerances of test sections, ±5%; imperfectness of correlation in handling the parameter effects, ±5%; and random and systematic instrumentation errors and various loop system characteristics, ±10%. The probability of a rod bundle reaching DNB for a given DNB ratio predicted by W-3 correlation has been evaluated and demonstrated for its use. The effect of a DNB rod in a rod bundle is considered as not detrimental and not contagious. The above statement is demonstrated and evidenced by a photograph of the bird's-eye view of DNB and two sets of experimental data.