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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.
Reiner Papp, Herbert Loser
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 228-235
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33787
Articles are hosted by Taylor and Francis Online.
Within the framework of the fuel cycle evaluation that has been conducted between 1981 and 1985 by Karlsruhe Nuclear Research Center in the Federal Republic of Germany, radiological safety has been considered an essential assessment criterion. The collective doses from normal operation turned out to exceed markedly the accidental doses associated with all stations at the back end of the fuel cycles. Both occupational and nonoccupational doses in the fuel cycle based on fuel reprocessing are higher than those from the once-through cycle, but radiological exposure of the population consists mainly of small individual doses that are only a small fraction of the doses due to natural background radiation.