|Fred said:
>slide explaining the isotopes found in a reactor
If the reactor is working properly I thought that the isotopes were contained in the Zircaloy casing
If the cladding remains intact, those fission products remain contained within the fuel rod (cladding and endplugs). There is some tramp uranium on fuel, but it is very low level. However, in the normal course of operation, some fuel rods do fail due to PCI, debris, perhaps unusual corrosion. In that case, Xe and Kr isotopes escape from the breach, and so do I-isotopes, Cs-isotopes, and a few others. If the fuel operates long enough with the breach or at power, and if the breach opens (guillotine break or axial split), then more of the solid fission products escape to the coolant, as the fuel matrix is oxidized.
In the current context, the fuel does not have to melt. Rather is only needs to split open to release a large inventory of fission products and allow the coolant (seawater) to interact with the fuel material. Normally the coolant is purified water, but seawater has NaCl and other salts. I don't know of any research that has looked at the solubility of irradiated fuel in seawater.
There are normally activitation products of Fe, Ni, Cr, and the activition of Ni is a source of Co (n,p reaction). The oxides of Fe, Ni and Cr come from the normal corrosion of stainless steel or Ni-alloys (structural materials), which are deposited on the fuel where they absorb neutrons and become activated. In addition, the control rod structures are mostly stainless steel, and some are used during operation to control reactivity. The introduction of seawater 'shocked' the system, and those activated products are released from the core to the coolant. One typically refers to a crud burst.
The presence of short-lived isotopes is somewhat of a concern. If the reactor, shutdown two weeks ago, and one is detecting short-lived isotopes, then one must ask if that is consistent with the reactor shutdown. If the detected levels are more consistent with a near term fission process, then when and where did that fissioning occur.
There are spontaneous fission in Pu-240 and Pu-242, and isotopes of Cm, Am. But are those fission rates sufficient to activate Na-23, Cl-35 and Cl-37, as well as producing I-132, I-134.
Meanwhile:
Unit 1 Dry Well 35.4 Sv/h or 3540 R/hr
Unit 2 Dry Well 43.2 Sv/h or 4320 R/hr
Unit 3 Dry Well 36.1 Sv/h or 3610 R/hr
This would be consistent with the release of fuel and corrosion products from the core into the coolant (seawater), which then found its way to the drywell (torus?).