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MARVEL team shares lessons learned through microreactor development
On June 1 at the American Nuclear Society’s Annual Conference in Denver, Colo., a team from Idaho National Laboratory presented a session titled “Lessons Learned from MARVEL Reactor Fabrication.” The presentation highlighted challenges that arose as they moved from design to manufacturing and assembly, with a focus on reactor part fabrication, Stirling engine implementation, and reactivity control system development.
John C. Statharas, John G. Bartzis, Demosthenes D. Papailiou
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 248-259
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34476
Articles are hosted by Taylor and Francis Online.
An improved version of the computer code THEAP-2, suitable for calculation of low flows (G < 50 kg/m2·s−1), is developed. The original code failed to provide reasonable agreement with existing experimental data. The discrepancies were attributed mainly to the drift-flux model, the dispersed flow transition criterion, and the correlations for estimating critical heat flux and minimum film boiling temperatures employed in the original code. The Electric Power Research Institute drift-flux model was used to correct these shortcomings and a new dispersed flow transition criterion was proposed. A review and an assessment of the available correlations of the temperatures resulted in the development of revised versions of these correlations. The changes improved the code’s ability to predict quantities such as the wall and vapor temperatures, the actual quality, and the vapor generation rate. The improvements can be attributed to the transition criterion introduced in the revised code.