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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry
By
AL Lowe, Jr Jr
AL Lowe, Jr Jr
1
Principal Engineer
,
Babcock & Wilcox
,
Lynchburg, Va
.
24505, editor
.
Search for other works by this author on:
GW Parry
GW Parry
2
Manager
,
Materials Technology, C-E Power Systems, Combustion Engineering
,
Windsor, Conn
.
06095, editor
.
Search for other works by this author on:
ISBN-10:
0-8031-0602-5
ISBN:
978-0-8031-0602-4
No. of Pages:
687
Publisher:
ASTM International
Publication date:
1977

Zircaloy-4 cladding tubes differing in texture only (Materials I and II were loaded simultaneously by internal pressure and axial forces at different stress ratios, α = axial stress, σa, and tangential stress, σt. Each stress ratio a was kept constant during the whole test, that is, from the beginning of elastic deformation to the fracture of specimens.

At room temperature the axial and tangential strains ϵa and ϵt, respectively, were measured as a function of σa and σt respectively (α = constant). These stress-strain diagrams were used to determine the apparent Young's moduli and the yield loci. At 400°C the yield locus was measured for Material I. Furthermore, for each stress ratio, α, those stresses σa and σt were measured at which fracture occurred. These “fracture” loci were determined for both materials at room temperature and 400°C.

Although the uniaxial data (stress ratio α = ∞) were very similar for both materials, a marked difference in yield and fracture behavior at a α ≠ ∞ was observed. Therefore, the criteria valid for isotropic materials turned out to be unsuitable for a satisfactory description of the measured data and relations.

1.
Dressler
,
G.
,
Matucha
,
K. H.
, and
Wincierz
,
P.
,
Canadian Metallurgical Quarterly
 0008-4433, Vol.
11
,
1972
, pp. 177–184.
2.
Dressler
,
G.
,
Matucha
,
K. H.
, and
Wincierz
,
P.
, “
Experimental and Theoretical Analysis of Anisotropic Mechanical Properties of Zircaloy Fuel Element Claddings
,” Preprints of the 2nd International Conference on Structural Mechanics in Reactor Technology,
Berlin, Germany
, 10–14 Sept. 1973, Vol. 1, Part C, Paper C 2/2.
3.
Dressler
,
G.
,
Drefahl
,
K.
,
Matucha
,
K. H.
, and
Wincierz
,
P.
in
Zirconium in Nuclear Applications, ASTM STP 551
,
American Society for Testing and Materials
,
1974
, pp. 92–103.
4.
Grewen
,
J.
,
Sauer
,
D.
, and
Wah1
,
H.-P.
,
Zeitschrift fur Metalikunde
, Vol.
61
,
1970
, pp. 430–436.
5.
Grewen
,
J.
,
Sauer
,
D.
, and
Wahl
,
H.-P.
,
Scripta Metallurgica
 0036-9748, Vol.
3
,
1969
, pp. 53–56.
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