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Additional info for Mgmt of Ageing of PWR Pressure Vessels (IAEA TECDOC-1120)
SSy Horiz. 2Sy Vert. 2Sy Horiz. 8 test Vert. 2Sy Horiz. 8 test Vert. 2Sy Loading Allowable limits Reactor vessel nozzle safe ends Normal + DBE Normal + DBA Nor+DBE+DBA Reactor vessel nozzle to shell juncture Reactor vessel support pads Normal + DBE Normal + DBA Nor+DBE+DBA Table Xffi shows the maximum range of primary plus secondary stress intensities compared against the allowable limits; also the table shows the calculated usage factors in fatigue. Note, the Code requirements are satisfied in all cases.
1 below. 66, "Requirements for thermal annealing of the RPV", the nuclear plant operators in the USA are provided a consistent set of requirements for the use of thermal annealing to mitigate the effects of neutron irradiation. 61 [pressure thermal shock (PTS) rule] and Appendix G of 10 CFR 50. Appendix G to 10 CFR Part 50, "Fracture toughness requirements", requires that the beltline materials have Charpy upper shelf energies of no less than 68 J (50 ft-lb) throughout the life of the vessel. C of the Appendix.
Not all the WWER pressure vessels were covered by austenitic stainless steel cladding on their whole inner surface: only approximately half of the WWER-440/V-230 pressure vessels were clad. However, all of the WWER-440/V-213 and WWER-1000 pressure vessels were covered on the whole inner surface. The cladding was made by automatic strip welding under flux with two layers — the first layer is made of a Type 25 chromium/13 nickel unstabilized austenitic material (Sv 07Kh25N13), and the second layer is at least three beads made of Type 18 chromium/10 nickel stabilized austenitic stainless steel (Sv 08Khl8N10G2B) to achieve a required total thickness of cladding equal to ~8 mm.
Mgmt of Ageing of PWR Pressure Vessels (IAEA TECDOC-1120)