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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.
Carol Braester, Roger Thunvik
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 60-70
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT88-A34117
Articles are hosted by Taylor and Francis Online.
A mathematical model is used to describe the migration of gas from radioactive waste repositories. Calculations are presented for rock properties characteristic of the Forsmark area. In Sweden, the repository of medium- and low-level radioactive waste is in fractured hard rock formations at a depth of ∼50 m below sea level. Chemical reactions in the stored waste produce hydrogen, which displaces the water from the fractures and migrates toward the surface, where it is finally released into the atmosphere. The lateral gas movement is considered negligible, and computations are performed under the assumption of vertical flow. Rock permeability was determined by flow tests in vertical boreholes. Calculations were performed for two cases: a constant gas flow rate corresponding to a gas production of 33 000 kg/yr and a constant pressure corresponding to a gas cushion of 0.5 m. For the considered permeability distribution, the breakthrough at the sea bottom occurred within ∼1 h. The gas-water displacement occurred mainly through high-permeability fractures, with practically no flow through the low-permeability fractures. It is concluded that the gas formed in the cavern is released into the atmosphere almost instantaneously and does not produce any significant overpressure in the cavern.