By International Atomic Energy Agency
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Extra info for Reactor water chemistry relevant to coolant-cladding interaction
This deviation to higher values has been attributed to irradiation enhancement of corrosion. L* WIKM1NGPOR7 b SAN ONOFRE . 2 V O MAINE VANlCC UtINAU. 1 O JOil CABHIBA Û 1A« to» COM II 0 O <> D JAY70N CORE III REACTOR A ,KWU RCACTORB , HWU M ACTOR C . 0X5 «VIDA« BURNW (HkkVMTU; Fig. 1 Maximum oxide layer thickness of PWR fuel rods versus burnup As seen on fig. 1 corrosion rates from reactors are usually higher than those expected from autoclave tests, and models in which the thermal barrier of the oxide to the heat transfer is calculated.
The key phenomenon at this stage is the quenching of the fuel rod. The temperature decrease at the end of the accident results in the beta-alpha transformation of oxidized Zircaloy if it has been into the beta phase. e. gases present in the affected grain boundaries; in extreme cases, this may completely destroy the pellet stack geometry; - Fragmentation of the oxygen-embrittled cladding under the thermal shock. These phenomena are extremely important because they lead to fuel dispersal into the core.
It might therefore be predicted that average fuel element deposition values would be similarly low. The reported "normal" ranges for the minor constituents in Mühleberg fuel crud are, however, very similar to those found on WSGHWR fuel. It is important in such comparisons that the feedwater, coolant and fuel element deposition data represent the same operational periods. This is uncertain for the Mühleberg data. The complexity of the transport picture is emphasized by the different time dependences of Co deposition on out-of-core surfaces in the RAPS-1 (CANDU-PHW) and in the WSGHWR (BWR).