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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.
Patrick Dumaz
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 946-955
Technical Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27688
Articles are hosted by Taylor and Francis Online.
Within the framework of the Three Mile Island Unit 2 Analysis Exercise, the calculation of phases I and 2 of the accident (0 to 174 min) was performed with the computer code CA THARE 1 and with a preliminary version of CATHARE 1/ICARE. The initial transient (0 to 30 min) is accurately predicted by CATHARE. From the thermal-hydraulic point of view, the remainder of phase 1 has also been very well simulated, even though for the overall problem, this particular part of phase 1 did not prove to be nearly as difficult. The analysis of phase 2 is limited because the computer code does not calculate material relocation. Nevertheless, cladding ballooning and cladding oxidation seem to be correctly predicted.