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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.
Robert J. Wolfgang, Rayford L. Patterson
Nuclear Technology | Volume 87 | Number 3 | November 1989 | Pages 616-623
Technical Paper | TMI-2: Remote Technology and Engineering / Nuclear Safety | doi.org/10.13182/NT89-A27713
Articles are hosted by Taylor and Francis Online.
The 1979 Three Mile Island Unit 2 accident caused fuel particles (fines) and debris to be transported throughout the reactor coolant system (RCS). Estimates of the fuel quantities in the RCS outside the reactor vessel boundary (defined as ex-vessel areas) have been developed. These estimates, in conjunction with as-low-as-reasonably-achievable considerations, were used to determine which ex-vessel areas required defueling.