Table of Contents

Foreword
Abstract
1 INTRODUCTION
2 THE DATABASES
3 ANALYSIS OF TENSILE DATA
4 ANALYSIS OF STRESS-RUPTURE DATA
5 ANALYSIS OF CREEP DATA
6 RECOMMENDATIONS OF ALLOWABLE
  STRESS INTENSITY VALUES
7 DISCUSSION
8 SUMMARY AND RECOMMENDATIONS
References
Appendix 1 - Estimation of the Time to
             Tertiary Creep
Appendix 2 - Time-Temperature Parametric
             Analysis
Appendix 3 - Notes on the Hot Tensile Curve
Acknowledgments

Abstract

Gives technical information necessary to update and expand appropriate ASME materials, construction and design codes for application in future Gen IV nuclear reactor systems that operate at elevated temperatures.

General Product Information

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