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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.
A. Cihat Baytaṣ
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 417-425
Technical Paper | RELAP/MOD2 / Heat Transfer and fluid Flow | doi.org/10.13182/NT90-A34405
Articles are hosted by Taylor and Francis Online.
Many computer codes are based on subchannel analysis, which is important for thermal-hydraulic analysis of the reactor core. Most of these codes make some assumptions to determine the axial velocity in the gap region (AVGR), but no real arguments have been given to justify these assumptions. A new way to determine the AVGR between two parallel single-phase flows that communicate by a lateral slot has been successfully incorporated in Tapucu’s subchannel analysis experiments.