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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
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.