Evaluation of the mechanical properties of an irradiated Type 347 stainless steel in-pile tube with a peak fluence of 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV)

Technical Report · Wed Aug 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/5713787· OSTI ID:5713787

Krupowicz, J. J.

Results of postirradiation mechanical testing of Type 347 stainless steel specimens machined from an Engineering Test Reactor in-pile pressure tube are presented. Tests included tensile and fracture toughness at room temperature, 600/sup 0/F, 800/sup 0/F, and 1000/sup 0/F, room temperature fatigue, and delayed failure stress rupture with stresses approaching the yield stress. Immersion density measurements were also made. Specimen fluences varied up to 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV). Although irradiation increased the strength, the material remained ductile and showed no evidence of notch or strain rate sensitivity, or embrittlement. Static and dynamic fracture toughness values were well above the minimum failure criterion requirements. At higher fluence all of the mechanical properties appear constant, indicating saturation of the irradiation damage. Extended in-pile service of such in-pile pressure tubes to 4 x 10/sup 22/ n/cm/sup 2/ (>1 MeV) was justified.

• Research Organization: Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States)
• DOE Contract Number: EY-76-C-11-0014
• OSTI ID: 5713787
• Report Number(s): WAPD-TM-1425; TRN: 80-000106
• Country of Publication: United States
• Language: English

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36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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PHYSICAL RADIATION EFFECTS
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DAMAGE
DENSITY
DUCTILITY
EMBRITTLEMENT
FAILURES
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HEAT RESISTANT MATERIALS
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IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
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NIOBIUM ADDITIONS
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360106* - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties
220600 - Nuclear Reactor Technology- Research
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