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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.
Nobuaki Ohnishi, Kiyomi Ishijima, Sadamitsu Tanzawa
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 331-341
Technical Paper | doi.org/10.13182/NSE84-A18587
Articles are hosted by Taylor and Francis Online.
The empirical correlations for subcooled film-boiling heat transfer during a reactivity-initiated accident in light water reactors are derived from inverse heat conduction calculations using the cladding surface temperatures measured in in-reactor experiments. The experimental data for cold startup conditions (subcoolings of ∼10 to 80 K and coolant velocities of ∼0 to 2 m/s at atmospheric pressure) and hot standby conditions (subcooling of ∼10 to 40 K, system pressures of 7.2 and 16 MPa, and system temperatures of 550 and 580 K) are used for this investigation. The present correlations are compared with existing correlations from ex-reactor experiments. The results of transient fuel behavior calculations with a computer code that included the present correlations are in good agreement with the corresponding measured data from the experiments.