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Extra resources for Accid. Anal. for Nuclear Powerplants
For a new plant, preliminary licensing analysis is performed prior to and as a condition of awarding the construction licence; and final licensing analysis is performed prior to and as a condition of awarding the operating license. For modifications to an existing plant, the final licensing analysis is performed prior to connection and/or use of the equipment; for major changes, it may be a requirement to submit a preliminary licensing analysis before construction of the modification. g. results on the effects of ageing) or from the refinement of predictive models.
However, in certain situations, the control systems may aggravate the transient or delay actuation of the protection features. The analyst needs to investigate these situations (not necessarily performing detailed calculations), starting with the assumption of full operability of control systems. The analyses also need to take into account conservative values for the delay in actuation of the safety systems, for protection set points and for key parameters of the safety system (such as the flow rates of the ECCS and the safety valves).
In particular, commercially developed CFD codes may not have been developed or validated specifically for reactor safety studies. Some of the subchannel codes have been combined with system thermohydraulic codes, while CFD codes have more typically been used alone. However, there have been some recent trends to merge CFD capabilities with currently available system level codes. 39 Containment codes may be less detailed than system thermohydraulic codes, but are also relatively independent of their design.
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