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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.
Peter J. Jensen, V. K. Chexal, Jason Chao, William H. Layman
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 252-273
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34140
Articles are hosted by Taylor and Francis Online.
The Nuclear Safety Analysis Center (NSAC) at the Electric Power Research Institute has a Generic Safety Analysis Program to help resolve high-priority safety issues. Several high-priority safety issues considered at NSAC were resolved at least in part through the use of the RETRAN computer code. These issues are pressurized thermal shock, anticipated transients without scram in both pressurized and boiling water reactors, steam generator tube rupture, and scram frequency reduction.