ASME STP-NU-041 : 2011
Current
The latest, up-to-date edition.
UPDATE AND IMPROVE SUBSECTION NH - ALTERNATIVE SIMPLIFIED CREEP-FATIGUE DESIGN METHODS
English
31-03-2011
Foreword
Executive Summary
1 INTRODUCTION
2 PREREQUISITES FOR EVALUATION
3 OUTLINE AND PREDICTABILITY OF NEWLY
PROPOSED CREEP-FATIGUE EVALUATION METHODS
4 POTENTIAL TO DEPLOYING THE METHODS
INVESTIGATED TO ASME-NH
5 CONCLUSIONS
References
Appendix 1 - Creep fatigue experiment data of Mod.9Cr-1Mo
Acknowledgments
Specifies work resulting from Cooperative Agreement DE-FC07-05ID14712 between the U.S. Department of Energy (DOE) and ASME Standards Technology, LLC (ASME STLLC) for the Generation IV (Gen IV) Reactor Materials Project.
| DocumentType |
Standard
|
| ISBN |
9780791833643
|
| Pages |
123
|
| PublisherName |
American Society of Mechanical Engineers
|
| Status |
Current
|
| ASME STP-PT-070 : 2014 | Design Guidelines for the Effects of Creep, Fatigue & Creep-Fatigue Interaction with Design-By-Analysis and Nondestructive Inspection Acceptance Criteria (STP-PT-070 - 2014) |
| AFCEN RCC-MR : 2007 | DESIGN AND CONSTRUCTION RULES FOR MECHANICAL COMPONENTS OF NUCLEAR INSTALLATIONS APPLICABLE TO HIGH TEMPERATURE STRUCTURES AND TO THE ITER VACUUM VESSEL |
| ASME STP-NU-013 : 2008 | Improvement of ASME Section III-NH for Grade 91 Negligible Creep and Creep-Fatigue (STP-NU-013 - 2008) |
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