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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
S. M. Ghiaasiaan, J. R. Muller, D. L. Sadowski, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 229-238
Technical Paper | doi.org/10.13182/NSE97-A24476
Articles are hosted by Taylor and Francis Online.
Critical discharge of highly subcooled water through a cylindrical channel with a 0.78-mm inside diameter and 0.78 mm in length was experimentally studied. The range of the initial water subcooling was 76 to 200 K, and the initial water pressure was in the range 0.5 to 5.2 MPa. The measured critical mass fluxes were compared with three models appropriate for application to critical flow in small and short channels.The experimental results confirm the significant effect of pressure losses on critical discharge rates in small channels. They indicate, however, that the frictional pressure losses in cracks may be considerably larger than losses predicted by the widely used correlations for rough channels. It is shown that models and correlations based on isentropic homogeneous equilibrium flow in the channel accurately predict the critical flow data, provided that the liquid initial stagnation pressure is adequately corrected for the channel entrance pressure loss.