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ASTM Selected Technical Papers
The Use of Small-Scale Specimens for Testing Irradiated Material
By
WR Corwin
WR Corwin
1
Metallurgical Engineer
, Metals and Ceramics Division,
Oak Ridge National Laboratory
,
Oak Ridge, Tennessee
;
symposium chairman and editor
Search for other works by this author on:
GE Lucas
GE Lucas
2
Associate Professor
, Department of Chemical and Nuclear Engineering,
University of California
,
Santa Barbara, California
;
symposium chairman and editor
Search for other works by this author on:
ISBN-10:
0-8031-0440-5
ISBN:
978-0-8031-0440-2
No. of Pages:
390
Publisher:
ASTM International
Publication date:
1986

The objective of miniaturized specimen technology is to enable the characterization of mechanical behavior while using a greatly reduced or minimum volume of material. The significance of this technology is obvious to the nuclear industry where neutron irradiation space is limited and irradiation costs scale with specimen volume. In addition, the substantial advantages resulting from application of this technology in non-nuclear industries are only beginning to be realized.

The initial development of a miniaturized disk bend test (MDBT) for extraction of post-irradiation mechanical behavior information from disk-shaped specimens no larger than transmission electron microscopy samples is described. Central loading with a hemispherically tipped punch is used to measure load/deflection curves to fracture. These load/deflection curves are simulated using finite element analysis. This approach to miniature mechanical property testing is shown to offer the potential for the derivation of uniaxial flow properties.

This paper primarily emphasizes the development of test techniques and procedures; however, results for the determination of uniaxial tensile behavior are presented to demonstrate the validity of the basic methodology. Recommended techniques for specimen design, specimen preparation, experimental design, experimental implementation, and data analysis are presented.

1.
Manahan
,
M. P.
, “
The Development of a Miniaturized Disk Bend Test for the Determination of Post-Irradiation Mechanical Behavior
,” Sc.D. thesis,
Massachusetts Institute for Technology
, Cambridge, Mass.,
1982
.
2.
Manahan
,
M. P.
,
Argon
,
A. S.
, and
Harling
,
O. K.
, “
The Development of a Miniaturized Disk Bend Test for the Determination of Post-Irradiation Mechanical Properties
,”
Journal of Nuclear Materials
 0022-3115, Vol.
103
and
104
,
1981
, pp. 1545-1550.
3.
Manahan
,
M. P.
,
Argon
,
A. S.
, and
Harling
,
O. K.
, “
Mechanical Behavior Evaluation Using the Miniaturized Disk Bend Test
,”
Sixteenth Quarterly Technical Progress Report on Damage and Fundamental Studies
, DOE/ER-0046/8, Oct.–Dec. 1981.
4.
Manahan
,
M. P.
, “
A New Post-Irradiation Mechanical Behavior Test—The Miniaturized Disk Bend Test
,” invited paper at the
American Nuclear Society 1982 Winter Meeting
,
17
11
1982
,
Washington, D.C.
; published in
Journal of Nuclear Technology
, Vol.
63
, No.
2
,
11
1983
.
5.
Harling
,
O. K.
,
Lee
,
M.
,
Sohn
,
D-S
,
Kohse
,
G.
, and
Lau
,
C. W.
The MIT Miniaturized Disk Bend Test
,” this publication, pp. 50-65.
6.
Annual Report on Alloy Development for Irradiation Performance in Fusion Reactors
,” Report MITNRL-003, 1978–1979.
7.
Szirmae
,
A.
and
Fisher
,
R. M.
, “
Specimen Damage During Cutting and Grinding
,” in
Techniques of Electron Microscopy, Diffraction, and Microprobe Analysis
, ASTM STP 372,
American Society for Testing and Materials
,
Philadelphia
,
1965
.
8.
Metallurgists to Industry
, “
Metallurgical Examination of EDM Cemented Carbide Samples
,” Report 47717,
27
10
1982
; available from
Agietron Corp.
, P.O. Box 469, 839 South Route 53, Addison, IL 60101.
9.
Gettleman
,
K.
, Ed., “
Wire EDM Challenges Aerospace
,”
Modern Machine Shop
.
10
1982
.
10.
Paxton
,
M. M.
, “
Mechanical Properties of Prototypic FTR Cladding—20% C.W. 316 Stainless Steel Tubing
,” HEDL-TME 71-59,
Hanford Engineering Development Laboratory
,
Richland, Wash.
,
04
1971
.
11.
Dooley
,
M.
,
Lucas
,
G. E.
, and
Sheckherd
,
J. W.
, “
Small Scale Ductility Tests
,” presented at
Second Topical Meeting on Fusion Reactor Materials
, 9–12 Aug. 1981,
Seattle, Wash.
, and to be published in a special topical report of the
Journal of Nuclear Materials
 0022-3115.
12.
Hibbitt
,
H. D.
,
Karlsson
,
B. I.
, and
Sorenson
,
E. P.
, “
ABAQUS: A General Purpose Finite Element Code
,” developed by
Hibbitt, Karlsson, and Sorenson, Inc.
,
Providence, R.I.
,
10
1982
.
13.
Rodal
,
J. J. A.
, “
Finite-Element Large-Deflection Finite-Strain Elastic-Plastic Transient Response Analysis of Structures
,” Ph.D. thesis,
Massachusetts Institute of Technology
, Cambridge, Mass.,
06
1979
.
14.
Rabinowicz
,
E.
,
Friction and Wear of Materials
,
Wiley
,
New York
,
1965
.
15.
Fish
,
R. L.
,
Cannon
,
N. S.
, and
Wire
,
G. L.
, “
Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel
,” in
Effects of Radiation on Structural Materials
, ASTM STP 683,
Sprague
J. A.
and
Kramer
D.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1979
, pp. 450-465.
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