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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.
Thomas M. Parker, Richard J. Kohrt, Sue I. Dederer, Larry E. Hochreiter, Walter R. Schwarz, Chon-Kwo Tsai, Michael Y. Young
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 227-237
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34243
Articles are hosted by Taylor and Francis Online.
Calculations were performed using a best-estimate computer code that determined the estimates of the 50th percentile peak cladding temperature (PCT) (1006 K) and the 95th percentile PCT (1263 K). These calculations included realistic WCOBRA/TRAC predictions of thermal-hydraulic phenomena occurring inside the vessel during upper plenum injection (UPI). The work done in applying realistic thermal-hydraulic methods for pressurized water reactors (PWRs) with UPI represents an important step in the maturation of advanced best-estimate computer codes like WCOBRA/ TRAC because their effect is finally being used in the licensing of operating plants, and their benefits are being used to make those PWRs more flexible and economic to operate.