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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
.
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ISBN-10:
0-8031-0539-8
ISBN:
978-0-8031-0539-3
No. of Pages:
631
Publisher:
ASTM International
Publication date:
1975

Cold-worked Type 316 stainless steel was irradiated at 500and 600°C with 1-MeV protons. The dependence of void formation on displacement damage, irradiation temperature, and microstructure was studied by transmission electron microscopy. Cold working delays the onset of swelling and reduces it, via a reduction in void size, at both irradiation temperatures. Inhomogeneity in the cold-worked microstructure leads to inhomogeneity in the disposition of voids. Swelling at 600°C is greater than at 500°C; the voids are less numerous but larger at the higher temperature. No change in the cold-worked microstructure can be detected by transmission electron microscopy after 500°C irradiation to 23 displacements per atom. Irradiation to a comparable damage level at 600°C results in almost complete elimination of the cold-worked microstructure. Comparison of the results is made with data from reactor irradiation experiments.

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,
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,
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, Jr.
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,” NEDO-13990,
General Electric Company
,
10
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.
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