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More from UWC 2020: Round 2
This year’s Utility Working Conference had a dynamic opening plenary and a packed roster of informative sessions. Following are recaps of some of the 2:00 p.m. (EDT) sessions that took place.
Don't miss Newswire's coverage of the opening plenary and the sessions at 12:00 pm.
N.M. Ghoniem, D.H. Berwald
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 439-444
Materials Engineering | dx.doi.org/10.13182/FST83-A22903
Articles are hosted by Taylor and Francis Online.
Lifetime estimates of blanket components are extremely useful during the design process of fusion reactor blankets. In this paper, we present a preliminary analysis for the performance of HT-9 in the blanket modules of a reference Tandem Mirror Hybrid Reactor (TMHR). We utilize the available data base for HT-9 as well as other ferritic alloys to develop approximate design equations for void swelling, the shift in the ductile-to-brittle-transition temperature (DBTT), and thermal creep rupture at high temperature. HT-9 is used in a relatively low temperature design (below 500°C) to give an allowable design stress on the order of 145 MPa for up to 10 operating years. A minimum structure temperature of 365°C is imposed on the design to ensure a good margin of safety against neutron embrittlement. As an added design feature, the moderate DBTT shifts are almost entirely eliminated by a 450°C anneal for 50–60 hours, once every year. The lifetime of the blanket is estimated to exceed 10 years, and is based on the maximum limit for total elastic plus inelastic strains.