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Sauter, A.; Cheverton, R.D.; Iskander, S.K.
Oak Ridge National Lab., TN (USA)1983
Oak Ridge National Lab., TN (USA)1983
AbstractAbstract
[en] The computer code OCA-I calculates the temperature distribution through the walls of a cylinder during a thermal transient and then performs a two-dimensional linear-elastic fracture-mechanics analysis to obtain stress-intensity factors for long surface flaws, considering both pressure and thermal loads. The code has been particularly useful in evaluating flaw behavior in reactor pressure vessels during overcooling accidents, but it has not previously treated the stainless steel cladding on the inner surface of the vessel as a discrete region. Although the cladding is quite thin compared with the base material, the large difference in thermal conductivity and coefficient of thermal expansion between the two materials results in a significant effect of the cladding on stress-intensity factors for surface cracks. Thus, the cladding was recently included as a discrete region in OCA-I
Original Title
PWR
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11 May 1983; 35 p; ORNL/TM--8649; Available from NTIS, PC A03/MF A01 as DE83011604
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Report
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