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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Latest News
NRC approves subsequent license renewal for Oconee
All three units at the Duke Energy’s Oconee nuclear power plant in South Carolina are now licensed to operate for an additional 20 years.
Yong-Seok Choi, Dong-Hoon Kam, Byong-Guk Jeon, Jong-Kuk Park, Sang-Ki Moon
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2711-2722
Research Article | doi.org/10.1080/00295639.2022.2132100
Articles are hosted by Taylor and Francis Online.
Insufficient thermal-hydraulic knowledge for analysis of a reactivity-initiated accident demands experiments of fast-transient flow boiling heat transfer from moderate- to high-pressure conditions. In this study, those experiments are conducted for vertical upward tube flows of pressurized water. The tube wall is joule heated by stepwise electric pulse power to achieve an abrupt wall heating condition. The applied pulse power is varied from 4.68 to 13.59 GW/m3, which is beyond the power required for steady-state critical heat flux (CHF) to occur. Rapid evolution of the boiling wall temperature is extracted from outer wall temperature data by solving an inverse heat conduction problem. As a result, with increasing the applied pulse power, the time to occurrence of departure from nucleate boiling gets shorter, and the corresponding peak heat flux increases over the steady-state CHF, which is evaluated at the same flow condition. A logarithmic relation between the wall heating rate and the CHF increment ratio is also demonstrated. The effects of pressure, inlet subcooling, and mass flux on the transient peak heat flux are also investigated. As the pressure increases, the nucleate boiling duration gets shorter with decreasing peak heat flux. On the other hand, as the inlet subcooling increases, the nucleate boiling duration gets longer, and the peak heat flux increases. Contrarily, the mass flux does not show any noticeable effects on the transient heat transfer evolution.