RE: heat output of SCRAMed nuclear reactor
March 20, 2011 at 9:38 am
(This post was last modified: March 20, 2011 at 10:19 am by lilphil1989.)
(March 16, 2011 at 2:13 pm)Chuck Wrote: Does anyone have any reference to the heat output of the nuclear fuel in a Diichi unit 1 type reactor after the control rods are inserted? I am trying to estimate how much water flow is required to cool it, how much salt must be building up in the reactor vessel, and whether there is any chance that seawater pumped into the reactor vessel to keep it cool would eventually deposite so much salt in the reactor that cooling fails do to clogging.
An order of magnitude estimate to start with would be about a MW/kg
This isn't reactor specific, but order of magnitude is probably all you'll get from a calculation of this type anyway, unless you know specifics of fuel rod size/shape, moderator geometry etc.
(March 20, 2011 at 9:38 am)lilphil1989 Wrote: An order of magnitude estimate to start with would be about a MW/kg
Ignore that, I was thinking of newly spent fuel.
Something around 10MW total would be more reasonable.
Galileo was a man of science oppressed by the irrational and superstitious. Today, he is used by the irrational and superstitious who claim they are being oppressed by science - Mark Crislip
