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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.
Corinne Bangil, Gérard Gambier, Michel Soldevila
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 344-349
Technical Paper | Probabilistic Safety Assessment and Risk Management / Fuel Cycle | doi.org/10.13182/NT89-A34218
Articles are hosted by Taylor and Francis Online.
Pressurized water reactor four-batch fuel management represents, in the present context, an economic optimum for the French standardized series of reactors. Plutonium recycling on an industrial scale has already started in France; therefore, it is essential to ascertain its compatibility with four-batch refueling requirements. In the survey considered, it is shown that a core refueled annually with 28 UO2 assemblies, having a 3.7% 235 U content and 12 mixed-oxide assemblies containing 6.5% plutonium, entirely satisfies safety criteria under normal operating conditions. A supplementary survey will be performed to assess its behavior under such accident conditions as steam line break and rod ejection.