Table of Contents

FOREWORD
ABSTRACT
1 SUMMARY
2 INTRODUCTION
3 NRC AND ACRS SAFETY ISSUES IN
  LICENSING REVIEW OF CRBR
4 CURRENT NRC SAFETY ISSUES FOR
  STRUCTURAL DESIGN OF VHTR AND GEN
  IV SYSTEMS
5 HOW REGULATORY ISSUES ARE ADDRESSED
  BY CURRENT ASME CODE CASES AND SECTION
  III SUBSECTION NH ôCLASS 1 COMPONENTS
  IN ELEVATED TEMPERATURE SERVICE
6 MATERIALS MODELS DESIGN CRITERIA AND
  ANALYSIS METHODS NEEDED IN THE ASME CODE
  TO COVER REGULATOR ISSUES FOR
  VERY-HIGH-TEMPERATURE SERVICE
ACKNOWLEDGMENTS
ABBREVIATIONS AND ACRONYMS
REFERENCES
Appendix A - NRC Licensing Review of CRBR - 1983
Appendix B - May 2, 2007 NRC Draft for Review

Abstract

Describes the safety issues relevant to the ASME Boiler and Pressure Vessel Code, including Section II, Section VIII, Section III Subsection NH (Class 1 Components in Elevated Temperature Service) and Code Cases that must be resolved in order to support licensing of Generation IV Nuclear Reactors, particularly Very-High-Temperature Gas-Cooled Reactors (VHTRs).

General Product Information

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