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Message Subject *** Fukushima *** and other nuclear-----updates and links
Poster Handle Anonymous Coward
Post Content
Been doing some reading.
Cracks in the reactors could have occurred when tepco flooded them with seawater. Reactors 1,2 and 3 were manufactured before the fix. Pre-1971. As far as I can tell from a quick look.
[link to en.wikipedia.org]


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wb

[link to www.phyast.pitt.edu]
[snip]

Pressurized Thermal Shock


The thick steel vessel housing the reactor is normally very hot because of the high temperature of the water inside (600°F). If, due to some malfunction, the inside is suddenly filled with cool water, the vessel experiences what is called "thermal shock." If it is then subjected to high pressure — producing pressurized thermal shock (PTS) — there is an increased tendency for the vessel to crack, rather than simply to stretch, if a small crack or imperfection already exists. The importance of PTS problems depends on quantitative details — how much of a thermal shock followed by how much pressure causes how much of an increased tendency to crack. Under ordinary conditions these quantitative details indicate that there is nothing to be concerned about. However, just as radiation can damage biological tissue, it can damage steel by knocking electrons and atoms out of their normal locations. This radiation damage to the reactor vessel aggravates its susceptibility to PTS.

Scientists recognized this problem over 20 years ago and they found a simple remedy for it — reducing the quantity of copper in the steel alloy from which the vessel is fabricated. This remedy was implemented in 1971, and all reactor vessels fabricated since that time have had no problems with PTS.

Reactor vessels fabricated before 1971 are kept under periodic observation to keep track of the problem. For many years, the NRC, burdened by other more urgent problems, put off considering PTS by adopting a very conservative screening criterion to indicate when further action on it would be undertaken. In 1981, time for action according to that criterion was only 1 or 2 years away in some reactors; hence, the NRC began to look into the problem in more detail by requesting information from various power plants.

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