Effect of Fast Reactor Fluence on Postirradiation Rupture of Type 316 Stainless Steel
- 1 July 1975
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 26 (3) , 297-306
- https://doi.org/10.13182/nt75-a24431
Abstract
Specimens of annealed Type 316 stainless steel were irradiated in Experimental Breeder Reactor II at temperatures ranging from 900 to 1450°F and to fluences from 0.2 to 7 × 1022 n/cm2 (En > 0.1 MeV). Uniaxial and biaxial creep tests were performed at 1000, 1100, 1200, and 1400°F with rupture times from 1000 h. The test data show that rupture life changes due to irradiation can be substantial. The stress, fluence, and temperature dependence of rupture life are reduced to a mathematical form, , where A and B are temperature-dependent terms and the term ti/tn is temperature and fluence dependent.Keywords
This publication has 4 references indexed in Scilit:
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- EBR-II DOSIMETRY TEST DATA ANALYSIS (REACTOR RUNS 31E AND 31F).Published by Office of Scientific and Technical Information (OSTI) ,1970
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