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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
Ronald D. Boyd, Sr.
Fusion Science and Technology | Volume 18 | Number 2 | September 1990 | Pages 317-324
Technical Paper | Blanket Engineering | doi.org/10.13182/FST90-A29303
Articles are hosted by Taylor and Francis Online.
Steady-State subcooled water flow boiling experiments were carried out in a uniformly heated horizontal circular channel with a 0.45-MPa exit pressure and with the mass velocity varying from 1.56 to 8.55 Mg/m2·s. Measurements of critical heat flux (CHF), local heat transfer, and pressure drop were made for a smooth-wall 1.02-cm-diam copper test section with a heated length-to-diameter (L/D) ratio of 49.0. For the same inlet temperature near 20.0°C, comparisons are made with previous data with L/D = 33.0, from 30.0 to 50.0, 96.6 (two cases), and 115.5. The exit pressures for the above data are 0.1, 0.45, 0.77, 1.59, and 1.67 MPa, respectively. When L/D is between 49.0 and 115.5, the L/D influence on CHF is found to be significant for a 1.02-cm channel diameter in subcooled flows for mass velocities above 4.0 Mg/m2·s. This finding is important since most researchers and designers assume minimal L/D influence when L/D is >30. Further, the present CHF and local heat transfer data extend the data base (CHF near 1000.0 W/cm2 and heat transfer coefficient near 70 000 W/m2·K) for large channel diameters near 1.0 cm and low exit pressures. These results will assist in preventing catastrophic conditions from occurring in future systems where the L/D influence might inappropriately be neglected. Finally, Gambill's correlation predicts CHF significantly above the present data for CHF below 500 W/cm2. Above 500 W/cm2, however, his correlation agreed well with both the present data and the data for L/D = 96.6.