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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.