History of flow-induced vibration incident occurred in Monju

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 363, Issue , 1998, Pages 103-108

  Morishita, Masaki ^a   Dozaki, Koji ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENTS; FATIGUE OF MATERIALS; FLOW OF FLUIDS; FRACTURE MECHANICS; NUCLEAR REACTORS;

MONJU FAST BREEDER REACTOR;

VIBRATIONS (MECHANICAL);

EID: 0031642239     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (8)

1. ASME Boiler and Pressure Vessel Code Section III, Division I, Appendix N, Article N-1300, ASME, 1995
2. ASME Power Test Code Supplement on Instruments and Apparatus -Part 3- Temperature Measurement, ASME, 1929
3. Hiroi, H. et al., 1996, ''Analysis of the Monju's Sodium Leak Accident and Investigation of the Cause", PNC Technical Review, No. 99, pp23, (in Japanese)
4. Itoh, W. et al., 1997, "Technical Report on Monju's Sodium Leak Incident", Journal of Atomic Energy Soc. of Japan, Vol. 39, No. 9, pp.704, (in Japanese)
5. Proposed Flow-induced Vibration Design Guide for Thermometer Wells, PNC TN94 10 97-042, PNC, 1997 (in Japanese)
6. th Pacific Basin Nuclear Conference, Kobe, Japan
7. th Int. Symp. on Fluid-structure Interactions, Aeroelasticity, Flow-induced Vibration and Noise, ASME, AD-Vol. 53-1, pp149
8. th Int. Symp. on Fluid-structure Interactions, Aeroelasticity, Flow-induced Vibration and Noise, ASME, AD-Vol. 53-1, pp139