ASME STP-NU-009 : 2008
ASME STP-NU-009 : 2008
GRAPHITE FOR HIGH TEMPERATURE GAS-COOLED NUCLEAR REACTORS
American Society of Mechanical Engineers
GRAPHITE FOR HIGH TEMPERATURE GAS-COOLED NUCLEAR REACTORS
American Society of Mechanical Engineers
Foreword
Abstract
1 INTRODUCTION
2 DEFINITIONS
3 GRAPHITE MODERATED GAS-COOLED
REACTORS
4 GRAPHITE
5 NEW GENERATION NUCLEAR GRAPHITES
6 SUMMARY
References
Acknowledgements
Gives the basic information relative bulk graphite production, structure, chemical properties, physical properties and neutron irradiation behaviour.
Document Type | Standard |
Status | Current |
Publisher | American Society of Mechanical Engineers |