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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.
J. C. Courtney, K. R. Ferguson, J. P. Bacca
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 30-41
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16199
Articles are hosted by Taylor and Francis Online.
The Hot Fuel Examination Facility/South, located at the Idaho National Engineering Laboratory, supports the nation’s nuclear energy program by providing a facility for destructive and nondestructive testing of reactor fuels and materials. Irradiated subassemblies and test devices are transferred from the adjacent Experimental Breeder Reactor II or other irradiation facilities into the hot cells. The reliability of those systems required to inhibit the release of radioactivity to the environment is reviewed, and the operations at the facility are described. For each of two hypothetical accidents, release fractions were developed for noble gases, iodines, cesiums, and particulate radionuclides based on realistic but conservative data. The methodologies of the International Commission on Radiological Protection (ICRP)— both ICRP-2 and ICRP-30—were used to determine the radiological consequences at off-site receptors. By either technique, dose commitments from inhalation and submersion were small fractions of current federal guidelines. The relative contribution of each radionuclide was determined; iodine and cesium were more significant than plutonium for the decay times considered.