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Extra info for Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessels (IAEA TECDOC-1470)
Stress corrosion cracks usually propagate perpendicular to the applied tensile stress. Cracks propagate with little or no attendant macroscopic plastic deformation and vary in degree of branching or formation of satellite cracks. Variation in crack morphology is a function of environment and microstructure as well as the type and orientation of the applied stresses. In general, increasing the applied stress level decreases the time to crack initiation. The material may exhibit a threshold stress intensity factor (KISCC) below, which SCC does not occur.
Of Nuclear Power Generation Facilities, Ministry of Economy and Industry Notification No. 501, Japan, October 1980. Japanese Society of Mechanical Engineers, JSME Codes for Nuclear Power Generation Facilities, JSME S NC1-2001, Rules on Design and Construction for Nuclear Power Plant, JSME Tokyo, August 2001 Japanese Industrial Technical Standards: Test Methods to Confirm Fracture Toughness of Nuclear Power Plant Components, JEAC 4206-2000, Japan Electric Association, 2000. Japanese Industrial Technical Standards: Test Methods to Confirm Fracture Toughness of Nuclear Power Plant Components, JEAC 4206-2003 Addendum, Japan Electric Association, 2003.
The triple sleeve sparger with piston rings is designed to counter these mechanisms by channeling the shedding vortices and any leakage flow to the downcomer without it contacting the nozzle wall. The welded spargers do not have a leakage issue and some have a double sleeve to counter the shedding vortex issue. The cause of cracking in the CRDRL nozzle blend area observed at several plants was attributed to mixing of cold CRD return flow with hot vessel water. 8] established actions to deal with this problem as well as that of feedwater nozzle blend area cracking caused by seal leakage.
Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessels (IAEA TECDOC-1470)