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Extra resources for Elevated-Temp Ferritic, Martensitic Steels - Applications to Future Nuclear Reactors
A533B) can operate. Although 2¼Cr-1Mo has been mentioned for this application, it appears that, like the T23 and T24 steels discussed in the previous section, the 3Cr-3WV and 3Cr-3WVTa steels would be better candidates for pressure vessels, piping, and other pressure boundary components of such a reactor. In the section sizes investigated to date, the 3Cr-3WV and 3Cr-3WVTa steels have strength over double the 345 MPa (50 ksi) used to design with the A533B steel. It also has strength advantages over the commercial T23 and T24 steels, as discussed below.
92 If it is accepted that at long rupture times at high temperature―low stresses―creeprupture life of any steel is ultimately determined by the inherent strength, which depends basically on the solid-solution strength, then there are obvious ways to increase the useful elevated-temperature strength. The difference in creep-rupture strength of different steels at high stresses (short rupture times) will be determined by differences in dislocation density, dispersion strengthening due to precipitates, and solid-solution strengthening.
116 smaller coolant gap, which means a smaller-diameter vessel, all other conditions being equal for the two steels. Furthermore, the composition of the 3Cr-3WV and 3Cr-3WVTa steels comply with the “reduced activation” criteria established in the fusion program. Current reactor pressure vessel steels contain significant amounts of radiation-sensitive elements, such as nickel and molybdenum, which result in significant activation of the steel. Reducedactivation materials contain only elements that, when activated during service, decay rapidly (typical long-decay-producing alloying elements Ni, Nb, Cu, and Mo are eliminated from the composition).