Abstract
The decommissioning of nuclear power plants is in the Slovak Republic an actual issue. In 2015 started the second decommissioning stage of nuclear power plant V1 in Jaslovské Bohunice. This stage involves the dismantling and segmentation of activated (reactor pressure vessel, reactor internals) and contaminated parts (steam generators, pressurizer). From this reason it is necessary to investigate the radiation situation in the vicinity of the component to be cut. The presented results show that during remote dismantling the exposure is small (compared with the fragmentation tasks). Moreover, when the pre-dismantling decontamination with decontamination factor of 100 is applied, the total collective effective dose is below the yearly limit of 20 mSv for workers.
Highlights
During decommissioning of nuclear power plants (NPP) several steps have to be carried out in order to achieve the desired end state in the planned time schedule
It is obvious that during these activities, the proper knowledge of the radiation situation and the optimization of radiation protection within the ALARA principle is crucial
In case of so-called large components the usual dismantling and transportation techniques have to be modified and many factors like site-specific conditions, availability of technical tools, the strategy of radioactive waste disposal have to be taken into account [1]
Summary
During decommissioning of nuclear power plants (NPP) several steps have to be carried out in order to achieve the desired end state in the planned time schedule. This includes mainly preparation for dismantling, dismantling of technological equipment, treatment and conditioning of resulting waste, storage and the final disposal of radioactive waste and in many cases the decontamination. In the Slovak Republic, the NPP V1 in Jaslovské Bohunice is currently in the 2nd and final decommissioning stage with planned duration between 2015-2025 [2] In this NPP, the VVER-440/230 reactor type (Russian type of pressurized water reactor) was used. From the construction point of view the vessel is made of carbon steel 22K; the collector material as well as the heat exchanging tube material is titanium stabilized austenitic steel with 0.08% carbon, 18% chromium, 10% nickel and less than 1% titanium [5]
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