Effects of irradiation temperature on embrittlement of nuclear pressure vessel steels
The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-cooled reactor (MHTGR) are being investigated, primarily because the operating temperatures are low [121 to 288[degrees]C (250--550[degrees]F)] compared to those for commercial light-water reactors (LWRs) [[approximately]288[degrees]C (550[degrees]F)]. The need for design data on the reference temperature (RT[sub NDT]) shift necessitated the irradiation at different temperatures of A 533 grade B class 1 plates, A 508 class 3 forging, and welds used for the vessel shell, vessel closure head, and vessel flange. This paper presents regular- and mini-tensile, Automated Ball Indentation (ABI), and Charpy V-notch (CVN) impact test results from five irradiation capsules of this program.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7368458
- Report Number(s):
- CONF-920673-18; ON: DE93015428
- Resource Relation:
- Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials, Denver, CO (United States), 21-25 Jun 1992
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
HTGR TYPE REACTORS
PRESSURE VESSELS
EMBRITTLEMENT
RADIATION EFFECTS
CHARPY TEST
FORGING
IRRADIATION
NEUTRON FLUENCE
STEEL-ASTM-A508
STEEL-ASTM-A533-B
TENSILE PROPERTIES
WELDED JOINTS
ALLOYS
CARBON STEELS
CONTAINERS
DESTRUCTIVE TESTING
FABRICATION
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LOW ALLOY STEELS
MATERIALS TESTING
MATERIALS WORKING
MECHANICAL PROPERTIES
MECHANICAL TESTS
REACTORS
STEELS
TESTING
210300* - Power Reactors
Nonbreeding
Graphite Moderated
360103 - Metals & Alloys- Mechanical Properties
360106 - Metals & Alloys- Radiation Effects