Lifetime estimates of a fusion reactor first wall by linear damage summation and strain range partitioning methods

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A generalized model of a first wall made of 20% cold-worked steel was examined for neutron wall loadings ranging from 2 to 5 MW/m/sup 2/. A spectrum of simplified on-off duty cycles was assumed with a 95% burn time. Independent evaluations of cyclic lifetimes were based on two methods: the method of linear damage summation currently being employed for use in ASME high-temperature design Code Case N-47 and that of strain range partitioning being studied for inclusion in the design code. An important point is that the latter method can incorporate a known decrease in ductility for materials subject to ... continued below

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Pages: 5

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Liu, K.C. & Grossbeck, M.L. January 1, 1979.

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A generalized model of a first wall made of 20% cold-worked steel was examined for neutron wall loadings ranging from 2 to 5 MW/m/sup 2/. A spectrum of simplified on-off duty cycles was assumed with a 95% burn time. Independent evaluations of cyclic lifetimes were based on two methods: the method of linear damage summation currently being employed for use in ASME high-temperature design Code Case N-47 and that of strain range partitioning being studied for inclusion in the design code. An important point is that the latter method can incorporate a known decrease in ductility for materials subject to irradiation as a parameter, so low-cycle fatigue behavior can be estimated for irradiated material. Lifetimes predicted by the two methods agree reasonably well despite their diversity in concept. Lack of high-cycle fatigue data for the material tested at temperatures within the range of our interest precludes making conclusions on the accuracy of the predicted results, but such data are forthcoming. The analysis includes stress relaxation due to thermal and irradiation-induced creep. Reduced ductility values from irradiations that simulate the environment of the first wall of a fusion reactor were used to estimate the lifetime of the first wall under irradiation. These results indicate that 20% cold-worked type 316 stainless steel could be used as a first-wall material meeting a 8 to 10 MW-year/m/sup 2/ lifetime goal for a neutron wall loading of about 2 MW-year/m/sup 2/ and a maximum temperature of about 500/sup 0/C.

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Pages: 5

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Dep. NTIS, PC A02/MF A01.

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  • 8. symposium on engineering problems of fusion research, San Francisco, CA, USA, 13 Nov 1979

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  • Report No.: CONF-791102-157
  • Grant Number: W-7405-ENG-26
  • Office of Scientific & Technical Information Report Number: 5418075
  • Archival Resource Key: ark:/67531/metadc1074030

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • January 1, 1979

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  • Feb. 4, 2018, 10:51 a.m.

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  • April 2, 2018, 1:15 p.m.

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Liu, K.C. & Grossbeck, M.L. Lifetime estimates of a fusion reactor first wall by linear damage summation and strain range partitioning methods, article, January 1, 1979; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1074030/: accessed December 13, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.