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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

Tensile, burst, and creep tests have been conducted at 320 to 400°C on Zircaloy tubing. The main emphasis was placed on moderately stress-relieved tubing although tubing ranging from cold worked to fully recrystallized conditions also was investigated.

Refined test techniques have been utilized to determine creep and burst loci. The anisotropy, which is not pronounced for standard tubing at elevated temperatures, is compared with texture measurements. The results are fitted with the Hill equation for anisotropic generalized stress. Creep rates are smaller under compressive stresses than under tensile stresses.

Primary creep decreases steadily as the final annealing temperature is increased. The steady state creep rate, however, shows a minimum for moderately stress-relieved material.

Burst elongation increases and yield strength decreases just at the onset of primary recrystallization while the uniform burst elongation increases at slightly higher annealing temperatures.

1.
Tenckhoff
,
E.
in
Zirconium in Nuclear Applications, ASTM STP 551
,
American Society for Testing and Materials
,
1974
, p. 179.
2.
Stehle
,
H.
, “
Progress in Zircaloy-4 Canning Technology for PWR-Fuel
,” Geneva Conference,
09
1971
. German additional paper, AED-CONF-71-100-26,
Zentralstelle fur Atomkernenergie-Dokumentation
,
Karlsruhe, Germany
.
3.
Stehle
,
H.
and
Steinberg
,
E.
,
Proceedings
, Deutsches Atomforum Reaktortagung,
Berlin
,
1974
, p. 352
4.
Kallstrom
,
K.
,
Anderson
,
T.
, and
Hofvenstam
,
A.
in
Zirconium in Nuclear Applications, ASTM STP 551
,
American Society for Testing and Materials
,
1974
, p. 160
5.
Schröder
,
H.
and
Holicky
,
M. J.
,
Journal of Nuclear Materials
 0022-3115, Vol.
33
,
1969
, p. 52
6.
Dressler
,
G.
and
Weidinger
,
H. G.
, “
KWU Fuel Cladding Technology and Quality Assurance
,” Presented at the International Atomic Energy Authority Seminar on Nuclear Fuel Quality Assurance,
Oslo, Norway
, 24–28 May 1976, to be published by
IAEA
,
Vienna, Austria
.
7.
Holicky
M. J.
and
Schroeder
,
J.
,
Journal of Nuclear Materials
 0022-3115, Vol.
44
,
1972
, p. 31
8.
Franklin
,
D. G.
and
Fisher
,
H. D.
, “
International Colloquium Measurement of Irradiation Enhanced Creep in Nuclear Materials
,”
Commission of the European Communities
, Petten, 5–6 May 1976.
9.
Dressler
,
G.
and
Matucha
,
K. H.
, personal information.
10.
Duncombe
,
E.
, WAPD-TM-984,
Bettis Atomic Power Laboratory
, Pittsburgh, Pa.,
1973
.
11.
Maki
,
H.
 et al
,
Proceedings
, International Conference on Nuclear Fuel Performance,
British Nuclear Energy Society
,
London
,
10
1973
, Paper 62.
12.
Hunt
,
C. E. L.
, Paper C 2/9, Third International Conference on Structural Mechanics in Reactor Technology,
London
,
09
1975
.
13.
Lucas
,
G. E.
and
Bement
,
A. L.
,
Journal of Nuclear Materials
 0022-3115, Vol.
55
,
1975
, p. 246.
14.
Senski
,
G.
,
Proceedings
, Deutsches Atomforum Reaktortagung,
Dusseldorf
,
1976
, p. 450
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