Comparison between instrumented precracked Charpy and compact specimen tests of carbon steels
The General Atomic Company High Temperature Gas-Cooled Reactor (HTGR) is housed within a prestressed concrete reactor vessel (PCRV). Various carbon steel structural members serve as closures at penetrations in the vessel. A program of testing and evaluation is underway to determine the need for reference fracture toughness (K/sub IR/) and indexing procedures for these materials as described in Appendix G to Section III, ASME Code for light water reactor steels. The materials of interest are carbon steel forgings (SA508, Class 1) and plates (SA537, Classes 1 and 2) as well as weldments of these steels. The fracture toughness behavior is characterized with instrumented precracked Charpy V-votch specimens (PCVN) - slow-bend and dynamic - and compact specimens (10-mm and 25-mm thicknesses) using both linear elastic (ASTM E399) and elastic-plastic (equivalent Energy and J-Integral) analytical procedures. For the dynamic PCVN tests, force-time traces are analyzed according to the procedures of the Pressure Vessel Research Council (PVRC)/Metal Properties Council (MPC). Testing and analytical procedures are discussed and PCVN results are compared to those obtained with compact specimens.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5537000
- Report Number(s):
- CONF-801281-1; ON: DE82006811; TRN: 82-008550
- Resource Relation:
- Conference: CSNI specialists meeting on instrumented precracked Charpy testing, Palo Alto, CA, USA, 1 Dec 1980
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
CLOSURES
HTGR TYPE REACTORS
PRESSURE VESSELS
REACTOR MATERIALS
FRACTURE PROPERTIES
YIELD STRENGTH
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STEEL-ASTM-A533-B
STEEL-ASTM-A537
TEMPERATURE DEPENDENCE
ALLOYS
CARBON STEELS
CONTAINERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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STEELS
210300* - Power Reactors
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360103 - Metals & Alloys- Mechanical Properties