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2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Breaking ground on a new approach to construction
The drive to Kairos Power’s reactor demonstration site in Oak Ridge, Tenn., is not only scenic—it’s historic. Nearly 85 years ago, roughly 30,000 construction workers transformed orchards and farmland into a key Manhattan Project site. Depending on your route, you may pass by one of the three gatehouses that were once military checkpoints controlling access to Atomic Energy Commission production facilities.
Hans K. Fauske
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE63-A17204
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Critical two-phase, steam - water flows have been measured in horizontal test sections with pipe diameters of 0.125 and 0.269 in. internal diameter (i.d.) over a range of qualities from 0.01 to 0.7, mass velocities from 500 to 4200 lb/sec-ft2, and critical pressures from 40 to 360 lb /in.2 absolute. The critical flow data and a theory for the critical flow phenomena have been discussed (1, 2). In this paper an analysis for the pressure drop data in the approach region to critical flow is presented. The flow mixture accelerates to critical flow at the end of the test sections, and thus the pressure drop data are for flow regimes in which both momentum and frictional losses are important. By utilizing the model developed for estimating critical discharge rates (1), two-phase friction factors were calculated from the experimental data. The friction factors obtained correlated well in terms of the two-phase quality and appear to be independent of flow rate, static pressure, and test geometry for the conditions examined.