Influence of fluence rate on radiation-induced mechanical property changes in reactor pressure vessel steels
- Materials Engineering Associates, Inc., Lanham, MD (USA)
This report describes a set of experiments undertaken using a 2 MW test reactor, the UBR, to qualify the significance of fluence rate to the extent of embrittlement produced in reactor pressure vessel steels at their service temperature. The test materials included two reference plates (A 302-B, A 533-B steel) and two submerged arc weld deposits (Linde 80, Linde 0091 welding fluxes). Charpy-V (C{sub v}), tension and 0.5T-CT compact specimens were employed for notch ductility, strength and fracture toughness (J-R curve) determinations, respectively. Target fluence rates were 8 {times} 10{sup 10}, 6 {times} 10{sup 11} and 9 {times} 10{sup 12} n/cm{sup 2} {minus}s{sup {minus}1}. Specimen fluences ranged from 0.5 to 3.8 {times} 10{sup 19} n/cm{sup 2}, E > 1 MeV. The data describe a fluence-rate effect which may extend to power reactor surveillance as well as test reactor facilities now in use. The dependence of embrittlement sensitivity on fluence rate appears to differ for plate and weld deposit materials. Relatively good agreement in fluence-rate effects definition was observed among the three test methods. 52 figs., 4 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Materials Engineering Associates, Inc., Lanham, MD (USA)
- Sponsoring Organization:
- USNRC
- OSTI ID:
- 6958889
- Report Number(s):
- NUREG/CR-5493; MEA-2376; ON: TI90009329; TRN: 90-026858
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NUCLEAR POWER PLANTS
PRESSURE VESSELS
RADIATION EFFECTS
STEELS
WELDING FLUXES
BRITTLENESS
CHARPY TEST
COMPARATIVE EVALUATIONS
DAMAGING NEUTRON FLUENCE
DUCTILITY
EXPERIMENTAL DATA
FAILURE MODE ANALYSIS
FRACTURE MECHANICS
IRRADIATION
MATERIALS TESTING
MECHANICAL PROPERTIES
METALLURGY
NEUTRON DOSIMETRY
PROGRESS REPORT
REACTOR SAFETY
SERVICE LIFE
TENSILE PROPERTIES
TEST REACTORS
WELDED JOINTS
ALLOYS
CONTAINERS
DATA
DESTRUCTIVE TESTING
DOCUMENT TYPES
DOSIMETRY
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL TESTS
MECHANICS
NEUTRON FLUENCE
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
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220200* - Nuclear Reactor Technology- Components & Accessories
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors