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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.
Min Lee, Chen Tsung Fan
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 43-57
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34702
Articles are hosted by Taylor and Francis Online.
Responses of a large, dry pressurized water reactor (PWR) containment in a station blackout sequence are analyzed with the CONTAIN, MARCH3, and MAAP codes. Results show that the predicted containment responses in a station blackout sequence of these three codes are substantially different. Among these predictions, the MAAP code predicts the highest containment pressure because of the large amount of water made available to quench the debris upon vessel failure. The gradual water boiloff by debris pressurizes the containment. The combustible gas burning models in these codes are briefly described and compared. In a station blackout sequence of a large, dry PWR containment, the discrete burning of combustible gases does not occur in the MAAP calculation because of the predicted high steam concentration. A comparison of the one-cell MARCH3 calculation and the six-cell CONTAIN calculation shows that the burning of combustible gases occurs earlier and has a larger impact on containment pressure in the MARCH3 calculation. For the cases analyzed, the simplified MARCH3 calculations always predict a higher containment pressure than the complicated CONTAIN calculations. The results of the CONTAIN calculation show that combustible gas detonation may occur in a local region of a large, dry PWR containment during a station blackout sequence.