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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.
Liq-Ji Yuan, Pao-Shan Weng, Cheng-Chang Chan
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 30-34
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34278
Articles are hosted by Taylor and Francis Online.
The radionuclides in the gaseous effluent, in the water coolant from the research reactor, and in the surroundings were detected with gamma-ray spectrometry with and without using the Compton suppression technique, depending on the activity levels detected. All gamma-ray spectra were taken at various reactor power levels to investigate the relationship between the gamma-ray activities and the power levels. The linear proportionality between the activities and the power levels is valid to a certain extent. Activity in the water coolant was quite high, so in situ measurement was replaced by the sampling technique. The radionuclide 24Na in the coolant was specifically determined as a function of reactor operating time, and it tended to saturate over time. No manmade radionuclides were present in the surroundings except for 137Cs as fallout.