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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.
Bernard L. Cohen
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 433-440
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A15969
Articles are hosted by Taylor and Francis Online.
The 1983 report of the Waste Isolation Systems Panel of the National Academy of Sciences (referred to as NAS-83) introduces a solubility limited dissolution (SLD) theory to estimate release rates from highlevel radioactive waste packages. It is pointed out that this theory, as presented, should apply equally well to each grain of average rock, but that when applied to that problem, it overpredicts the observed dissolution rate of SiO2 by seven orders of magnitude. The SLD theory also predicts that cesium and other trace elements are leached out of rock grains orders of magnitude more rapidly than the SiO2; it is shown that this is clearly contrary to the experimentally observed situation. Other shortcomings of the NAS-83 treatment are pointed out. Modifications to the theory that avoid these large discrepancies are suggested; when applied to the waste problem, they pose some very important questions that should be answered before proceeding with waste management problems. For example, they suggest that reprocessing may reduce the hazards from waste by a factor of 10 million, and that synroc may be millions of times more secure against leaching than waste glass.