Influence of fluence rate on radiation-induced mechanical property changes in reactor pressure vessel steels

Technical Report · Thu Mar 01 04:00:00 EST 1990

DOI:https://doi.org/10.2172/6958889· OSTI ID:6958889

Hawthorne, J R; Hiser, A L ^[1]

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1. 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: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Materials Engineering Associates, Inc., Lanham, MD (USA)
• Sponsoring Organization: NRC
• OSTI ID: 6958889
• Report Number(s): NUREG/CR-5493; MEA--2376; ON: TI90009329
• Country of Publication: United States
• Language: English

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36 MATERIALS SCIENCE
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ALLOYS
BRITTLENESS
CHARPY TEST
COMPARATIVE EVALUATIONS
CONTAINERS
DAMAGING NEUTRON FLUENCE
DATA
DESTRUCTIVE TESTING
DOCUMENT TYPES
DOSIMETRY
DUCTILITY
EXPERIMENTAL DATA
FAILURE MODE ANALYSIS
FRACTURE MECHANICS
IMPACT TESTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MECHANICS
METALLURGY
NEUTRON DOSIMETRY
NEUTRON FLUENCE
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
POWER PLANTS
PRESSURE VESSELS
PROGRESS REPORT
RADIATION EFFECTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SERVICE LIFE
STEELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TENSILE PROPERTIES
TEST REACTORS
TESTING
THERMAL POWER PLANTS
WELDED JOINTS
WELDING FLUXES