ASME STP-NU-010 : 2008

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

This Report:1) identifies 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);2) describes how Subsection NH addresses these issues; and 3) identifies the needs for additional criteria to cover unresolved safety concerns for very-high-temperature service.