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ASTM Selected Technical Papers
Properties of Reactor Structural Alloys After Neutron or Particle Irradiation
By
CJ Baroch
CJ Baroch
1
Manager
,
Materials & Chemical Technology Laboratory, Babcock & Wilcox Company, Lynchburg Research Center
,
Lynchburg, Va. 24505
.
Search for other works by this author on:
ISBN-10:
0-8031-0539-8
ISBN:
978-0-8031-0539-3
No. of Pages:
631
Publisher:
ASTM International
Publication date:
1975

Results from elevated temperature, strain controlled fatigue tests with and without hold periods at peak tensile strain on specimens cut from Type 304 stainless steel plates welded using Type 308 stainless weld wire with controlled residual elements (CRE) are reported. Specimens were irradiated to fluences of 0.1 to 1.1 × 1022 neutrons (n)/cm2, E > 0.1 MeV at 450 and 600°C, while the postirradiation test temperature was 482 and 593°C respectively. Irradiation reduced the fatigue life of the weld metal at 593°C by about one half in the low cycle region (> 5 000 cycles to fail), but cyclic life was equivalent or slightly superior to the unirradiated material in the higher cycle region (> 10 000 cycles to fail). At 482°C and at the lower fluence, the fatigue behavior of the irradiated specimens was almost equivalent in the low cycle region and superior in the high cycle region. Introducing tensile hold periods at the peak strain of each fatigue cycle of the 593°C tests resulted in reductions in the fatigue life but at a much lesser rate than the base (parent) metal. Irradiation further reduced the life of the hold time tests. Hold periods had no significant effect at 482°C. Orientation effects were seen in all weld metal tests with the parallel orientation (specimen axis parallel to the weld seam) showing a superiority in cyclic life over those taken transverse to the welding direction.

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,
American Society of Mechanical Engineers
, Code Case 1331–8.
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Brinkman
,
C. R.
and
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,
G. E.
, “
Heat-to-Heat Variations in the Fatigue and Creep-Fatigue Behavior of AISI Type 304 Stainless Steel, and the Fatigue Behavior of Type 308 Stainless Steel Weld Material
,” Report ANCR-1097,
Aerojet Nuclear Company
,
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,
C. R.
,
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,
G. E.
, and
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, “
Comparison of the Strain Controlled Low Cycle Fatigue Behavior of Stainless Type 304/308 Weld and Base Metal
,” International Conference on Creep and Fatigue in Elevated Temperature Applications, sponsored by the
American Society for Testing and Materials, American Society of Mechanical Engineers, and Institution of Mechanical Engineers
,
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, 23–27 Sept. 1973 and
Sheffield, United Kingdom
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,
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,
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,” ORNL-4936,
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,
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,
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, and
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, pp. 297–307.
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,” Report ANCR-1078,
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,
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,
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,
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, and
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,
American Society for Testing and Materials
,
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,
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,
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,
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, and
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,
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, “
Creep Properties of a Type 308 Stainless Steel Pressure Vessel Weld with Controlled Residual Elements
,” International Conference of Creep and Fatigue in Elevated Temperature Applications, sponsored by the
American Society for Testing and Materials, American Society of Mechanical Engineers, and Institution of Mechanical Engineers
,
Philadelphia, Pa.
, 23–27 Sept. 1973 and
Sheffield, United Kingdom
,
04
1974
, preprint available from ASTM.
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