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Atlanta, GA|Atlanta Marriott Marquis
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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
Werner Maschek, Margaret W. Asprey
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 330-336
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33291
Articles are hosted by Taylor and Francis Online.
The behavior of a homogeneous reactor core of the 300-MW(electric) class has been evaluated during the pretransition and transition phases of a hypothetical loss-of-flow accident without scram. The SIMMER-II code has been used to track core material redistribution processes, which can lead to recriticalities and secondary nuclear power excursions. One of the key questions of core disruptive accident analysis is if core meltdown inevitably leads to a bottled-up core situation with its energetics potential or if various phenomena exist (as material discharge of hot fuel through the axial blankets, drop-in of blanket material into the core region, etc.) that prevent the accident progression into a bottled-up transition phase pool. The analyses for the specified reactor design show that, taking into account the aforementioned phenomena, the dominant accident path will lead to the postaccident heat removal phase directly from the pretransition phase. The accident path into the transition phase with a bottled-up core situation and its energetics potential might thereby be avoided.