Theoretical model for predicting the relative timings of potential failures in steam generator tubes of a PWR during a severe accident

Bansah, C.Y.; Akaho, E.H.K.; Ayensu, A.; Adoo, N.A.; Agbodemegbe, Vincent Yao; Alhassan, Erwin; Della, R.

doi:10.1016/j.anucene.2013.03.013

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2013

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“…Bansah et al calculated the recirculation ratio and the mixing fraction of natural circulation, and the circulation flow characteristics in the nuclear power plant accident of station-blackout accidents. The results show the natural circulation flow can delay the heat transfer tube rupture time [6] . The corrosion problem of the HTT rupture was presented in these works, but it did not show clearly the mechanism of corrosion cracking, yet.…”

Section: Introductionmentioning

confidence: 94%

Stress Corrosion Analysis of Steam Generator Tube of Nuclear Power Plant by Finite Elements

Jiang

Zhang

Wang

2013

AMM

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The steam generator is operated under the pressure of 15.5MPa and the temperature 327°C. Under this working condition the junction of the heat transfer tube and tube-sheet is accident-prone areas of the steam generator. By using ANSYS to carry out a thermal structure coupling analysis on the junction, it is found that a large tensile stress along axial and tangential directions occurs on outer surface of the heat transfer tube and is located at the region of 2.0 mm to 6.0 mm high over the tube-sheet. The stress attributes to the rapidly change of temperature on the tube outer surface and leads to the stress corrosions.

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Section: Introductionmentioning

confidence: 94%