PRESSURIZED WATER REACTOR STEAM GENERATOR TUBE FRETTING AND FATIGUE WEAR CHARACTERISTICS.

American Society of Mechanical Engineers (Paper)

Volumn , Issue , 1986, Pages

  Hofmann, P J ^a   Schettler, T ^a   Steininger, D A ^a  

^a West Ger ^*

Author keywords

[No Author keywords available]

Indexed keywords

NUCLEAR POWER PLANTS; NUCLEAR REACTORS, PRESSURIZED WATER; STEEL CORROSION - FRETTING;

FATIGUE WEAR; FRETTING WEAR; TEST DATA COMPARISON;

STEAM GENERATORS;

EID: 0022887054     PISSN: 04021215     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (23)