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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.
Donald G. Schweitzer, Cesar A. Sastre
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 305-312
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34298
Articles are hosted by Taylor and Francis Online.
At present, only one concept, the Swedish design utilizing a thick-walled copper waste package, has been accepted as being capable of isolating high-level waste for hundreds of thousands of years in a granite-type repository. Theoretical arguments show that after the relatively short times required for salt consolidation selfshielded thin-walled copper waste packages have no significant failure or degradation reactions in anoxic neutral and acid brines. Thermodynamic analyses of reactions after consolidation (constant-volume reactions under lithostatic pressures in the absence of oxygen) show that miniscule amounts of metal reacting with brine can produce very large hydrogen pressures. For copper waste packages, almost no consumption of copper is required to produce the small equilibrium hydrogen pressure needed to prevent reaction. Reaction under these conditions no longer depends on poorly understood corrosion mechanisms, but results from hypothetical mechanisms that allow the equilibrium hydrogen to migrate away from the waste package. Analyses of gamma radiolysis and diffusion processes show that in an array of thousands of waste packages removal of hydrogen from the outer packages should be negligible for a properly selected salt repository.