Steam generator tube integrity program. Phase I report. [PWR]-Reference-Cited by-同舟云学术

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Steam generator tube integrity program. Phase I report. [PWR]

Published:1979-09-01 Issue: Volume: Page:
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Author:

Alzheimer J.M.,Clark R.A.,Morris C.J.,Vagins M.

Publisher

Office of Scientific and Technical Information (OSTI)

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Limit load analyses of helical coiled steam generator tubes with a volumetric flaw;Fatigue & Fracture of Engineering Materials & Structures;2012-06-12

2. Determination of the critical crack length for steam generator tubing based on fracture-mechanics-based method;Annals of Nuclear Energy;2011-09

3. Structural Integrity Assessment of Steam Generator Tube by the Use of Heterogeneous Finite Element Method;Journal of Pressure Vessel Technology;2008-09-10

4. Structural Integrity Estimates of Steam Generator Tubes Containing Wear-Type Defects;Journal of Pressure Vessel Technology;2008-06-16

5. Rupture pressure of wear degraded alloy 600 steam generator tubings;Journal of Nuclear Materials;2008-02

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