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Additional resources for Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessels (IAEA TECDOC-1470)
35 σy. 8 CL for limit analysis (CL denotes collapse load) No evaluation of secondary stresses (including thermal stresses) is required since they are self-relieving. These conditions need not be considered in the component fatigue evaluation since limited to a total of 25 occurrences. 5. Design and analysis against non-ductile failure (heatup and cooldown limit curves for normal operation) At the recommendation of the Pressure Vessel Research Committee, the ASME Boiler and Pressure Vessel Code introduced criteria into Section III — Nuclear Power Plant Components — to provide assurance against brittle failure.
Allowable stresses, based on perfect plasticity and limit design theory, may be considered as a floor below which a vessel made of any sufficiently ductile material will be safe. The actual strain-hardening properties of specific materials will give them larger or smaller margins above this floor. 23 Fig. 3-2 Idealized stress-strain relationship. FIG. 3-3. Limit stress for combined tension and bending (rectangular section). 24 In a structure as simple as a straight bar in tension, a load producing yield stress, Sy, results in “collapse”.
Description of mechanism Stress corrosion cracking is the sub-critical crack growth of susceptible alloys under the influence of a corrosive environment. The three factors necessary for stress corrosion to occur are tensile stress, susceptible material, and a corrosive environment as shown in Fig. 4-1. IGSCC Occurs Susceptible material High tensile stress Corrosive environment FIG. 4-1. Factors of Stress Corrosion Cracking. Tensile stresses causing SCC are typically at material yield strength levels.
Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessels (IAEA TECDOC-1470)