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KMID : 0371820000320020099
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Nuclear Engineering and Technology
2000 Volume.32 No. 2 p.99 ~ p.107
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Probabilistic Structural Integrity Assessment of a Reactor Vessel Under Pressurized Thermal Shock
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Ji-Ho Kim
Yong-Wan Kim/Tae-Wan Kim/Hyung Huh/Jong-ln Kim
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Abstract
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A probabilistic integrity analysis method is presented for a reactor vessel under pressurized thermal shock(PTS) based on Monte Carlo simulation. This method can be applied to the structural integrity assessment of a reactor vessel subjected to pressurized thermal shock where the coolant temperature transient cannot be expressed explicitly as a time function. An axially or circumferentially oriented infinite length surface crack is assumed to be in the beltline weld region of the rector vessel's inside surface. The random variables are the initial crack depth, neutron fluence on the vessel's inside surface, the copper and nickel content of the vessel materials, R
TNDT , KIC , and K/aub la/. The reliability of a sample reactor vessel under PTS is assessed quantitatively and the influence of the amount of neutron fluence is also examined by applying the present method.sent method.
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KEYWORD
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probability, fracture, pressurized thermal shock, monte carlo simulation,
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