Table of Contents

Foreword
Abstract
PART I
1 SELECTION OF CANDIDATE MATERIALS AND
  CORRESPONDING TIME AND TEMPERATURE
  OPERATING CONDITIONS
2 REVIEW OF AVAILABLE JAPANESE DATA ON
  HASTELLOY XR AND INCONNEL 617 AND REQUIRED R&D
3 ESTIMATION OF STRENGTH CHARACTERISTICS
References - Part I
Part II
1 SELECTION OF CANDIDATE MATERIALS
References - PART II, Section 1
2 REVIEW OF AVAILABLE DATA FOR CANDIDATE MATERIALS
3 ESTIMATE OF STRENGTH CHARACTERISTICS
References - Part II, Sections 2&3
Appendix A - U. S. Patent of Hastelloy XR
Appendix B - Tests and Estimated Costs
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