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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.
John A. Andersen
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 75-83
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33755
Articles are hosted by Taylor and Francis Online.
A method is presented for correlating a tracer gas leakage rate to the potential particulate radioactive material (RAM) release from packages for the shipment of RAM, for those cases where a gas leak measurement is used and there is no measurable particulate release. The correlation method involves a calculational technique relating the measured gas leakage to capillary flow, then to the design and dimensions of the actual seal, and then to the minimum size of the particulate material being contained. Numerous examples are cited. This method is useful both in the evaluation of results obtained during regulatory-required testing, and in the process of applying for package certification or licensing. It is indicated that relatively large measured leaks in containment vessels may be analogous to extremely small defects in the actual seal, and to minute releases of RAM.