Table of Contents

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

Abstract

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.

General Product Information

Published
Document Type	Standard
Status	Current
Publisher	American Society of Mechanical Engineers
Pages
ISBN