Study of Stress Corrosion Cracking Behavior on the Shaft Steel of Reactor Cooling Pump

Technical documentation

J.-H. Huang and G.-P. Yu

Final report to the National Science Council ROC Final report to the National Science Council ROC

2000

Abstract

Stress Corrosion Cracking Behavior;Shaft Steel;Reactor Cooling Pump

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Title: Study of Stress Corrosion Cracking Behavior on the Shaft Steel of Reactor Cooling Pump
Creators - without role: J.-H. Huang - 國立清華大學原子科學院工程與系統科學系
G.-P. Yu
Publication Details: Final report to the National Science Council ROC Final report to the National Science Council ROC
Identifiers: 9957770385306774
Academic Unit: Department of Engineering and System Science, College of Nuclear Science, National Tsing Hua University
Language: Traditional Chinese
Resource Type: Technical documentation