The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators
- Author(s):
- John M. Dyke
- Publication title:
- 12th International Conference on Nuclear Engineering, Volume 3
- Title of ser.:
- ASME Symposia Volumes
- Ser. no.:
- ICONE 12(3)
- Pub. Year:
- 2004
- Vol.:
- 3
- Paper no.:
- ICONE12-49059
- Page(from):
- 393
- Page(to):
- 396
- Pages:
- 4
- Pub. info.:
- New York: American Society of Mechanical Engineers
- ISBN:
- 9780791846896 [079184689X]
- Language:
- English
- Call no.:
- A11658/12
- Type:
- Conference Proceedings
Similar Items:
|
1
Conference Proceedings
Comparison of Predicted and Observed Fretting-Wear Damage in Nuclear Steam Generators
American Society of Mechanical Engineers |
7
Conference Proceedings
Computation of Two-Phase Flow in Steam Generator Using Domain Decomposition and Local Zoom Methods
American Society of Mechanical Engineers |
|
2
Conference Proceedings
Comparison of Predicted and Observed Fretting-Wear Damage in Nuclear Steam Generators
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
|
3
Conference Proceedings
Thermalhydraulic Analysis of the Steam Generator Design for the 700 MWe Indian Nuclear Power Plant
American Society of Mechanical Engineers |
Society of Photo-optical Instrumentation Engineers |
|
American Society of Mechanical Engineers |
10
Conference Proceedings
Non-Linear Time Domain Method to Predict Tube-to-Tube Support Plate Fretting Wear in Steam Generators
American Society of Mechanical Engineers |
|
American Society of Mechanical Engineers |
11
Conference Proceedings
Non-Linear Time Domain Method to Predict Tube-to-Tube Support Plate Fretting Wear in Steam Generators
American Society of Mechanical Engineers |
|
6
Conference Proceedings
Fitness-for-Service Assessment for Steam Generator Tube Fretting at Darlington Nuclear Generating Station
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |