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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry
By
JH Schemel
JH Schemel
1
conference chairman
Search for other works by this author on:
TP Papazoglou
TP Papazoglou
2
The Babcock & Wilcox Company
,
Lynchburg, Va. 24505
;
editorial chairman
.
Search for other works by this author on:
ISBN-10:
0-8031-0601-7
ISBN:
978-0-8031-0601-7
No. of Pages:
637
Publisher:
ASTM International
Publication date:
1979

The mathematical model MATMOD-Z has been built to permit computer simulation of in-reactor Zircaloy deformation behavior. The 250 to 450°C temperature range is covered together with a wide range of possible strain rates, accrued strains, and as-fabricated material conditions. MATMOD-Z is comprised of coupled time-rate equations in stress, strain, temperature, fast neutron flux, and certain material state variables. These latter quantities are: Fdef, representing the friction stress due to isotropic deformation-induced obstacles; Fsol, representing the friction stress due to solute drag; R, the “rest stress,” or back stress due to directional obstacles; and f2, the Kearns texture number in the direction bisecting the basal pole intensity peaks. Comparison of MATMOD-Z predictions to independent test data indicate a distribution of errors in predicted stress given complex strain-time-temperature history with standard deviation of the order of 17 percent. The most important source of error is thought to lie in an effect not treated in the current model, namely, increased solute drag with increasing dislocation density.

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,
D.
 et al
, “
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,” EPRI NP-500,
Electric Power Research Institute
,
05
1977
.
2.
Sherby
,
O. D.
and
Miller
,
A. K.
, “
Development of the Materials Code MATMOD (Constitutive Equations for Zircaloy)
,” EPRI NP-567,
Electric Power Research Institute
,
12
1977
.
3.
Ballinger
,
R. G.
,
Lucas
,
G. E.
, and
Pelloux
,
R. M.
Effects of Anisotropy and Irradiation on the Deformation Behavior of Zircaloy 2
,” EPRI NP-785,
Electric Power Research Institute
, to be published.
4.
Ballinger
,
R. G.
, “
The Anisotropic Mechanical Behavior of Zircaloy 2
,” MS. Thesis,
Massachusetts Institute of Technology
, Cambridge, Mass.,
09
1977
.
5.
Lucas
,
G. E.
, “
Effects of Anisotropy and Irradiation on the Creep Behavior of Zircaloy-2
,” Sc.D. Thesis,
Massachusetts Institute of Technology
, Cambridge, Mass.,
01
1978
.
6.
Miller
,
A. K.
, in
Zirconium in the Nuclear Industry. ASTM STP 633
,
American Society for Testing and Materials
,
1977
, p. 523.
7.
Miller
,
A. K.
and
Shih
,
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,
Journal of Engineering Materials and Technology
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99-H
,
1977
, p. 275.
8.
Miller
,
A. K.
, “
Predictions of Localized Plastic Flow Conditions in Irradiated Zircaloy Using a Unified Phenomenological Model
,” 4th International Conference on Structural Mechanics in Reactor Technology,
San Francisco
,
08
1977
, paper #C3/8.
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,
C. F.
,
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, and
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, and
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11.
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,
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,
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,
American Society for Testing and Materials
,
1970
, p. 215.
15.
Liu
,
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and
Bement
,
A. L.
, “
A Regression Approach for Zircaloy-2 In Reactor Creep Constitutive Equations
,”
4th International Conference on Structural Mechanics in Reactor Technology
, Paper C3/3,
08
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.
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Garofalo
,
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 et al
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,
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,
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,
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,
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,
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and
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,
Acta Metallurgica
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26
,
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, pp. 289–304.
22.
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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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,
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,
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,
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25.
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,
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, No.
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,
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,
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,
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,
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,
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27.
Van Swam
,
L.
and
Pelloux
,
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, “
Relationship between Contractile Strain Ratio R and Texture in Zirconium Alloy Tubing
,” To be published in
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28.
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,
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, et al
,
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, Vol.
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,
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29.
Krieg
,
R. D.
, “
Numerical Integration of Some New Unified Plasticity—Creep Formulations
,”
4th International Conference on Structural Mechanics in Reactor Technology
,
San Francisco
,
08
1977
, paper no. M6/4.
30.
Shih
,
C. F.
and
Lee
,
D.
, “
Further Developments in Anisotropic Plasticity
,”
General Electric Company
Report No. 77CRD248,
11
1977
.
31.
Zaverl
,
F.
, Jr.
, and
Lee
,
D.
, “
Constitutive Relations for Nuclear Core Materials
,”
General Electric Company
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32.
Lee
,
D.
and
Zaverl
,
F.
, “
A Generalized Strain Rate Dependent Constitutive Equation for Anisotropic Metals
,”
General Electric Company
Report No. 77CRD280,
01
1978
.
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