Skip to Main Content
Skip Nav Destination
ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: 20th International Symposium
Editor
Suresh K. Yagnik
Suresh K. Yagnik
Symposium Chairperson and STP Editor
1
Electric Power Research Institute (EPRI)
,
Palo Alto, CA,
US
Search for other works by this author on:
Michael Preuss
Michael Preuss
Symposium Chair and STP Editor
2
The University of Manchester Manchester
,
GB
;
Monash University
,
Clayton/Melbourne,
AU
Search for other works by this author on:
ISBN:
978-0-8031-7737-6
No. of Pages:
928
Publisher:
ASTM International
Publication date:
2023

The α grains in hot extruded Zr-2.5Nb pressure tubes are highly elongated in the extrusion direction (tens of microns in length), slightly elongated in the hoop direction (on the order of a few microns), and very thin in the direction of the tube wall (<1 μm). Because diametral creep may limit the operational life of pressure tubes in CANDU reactors, studies to understand the effect of these grain dimensions on creep have been ongoing. In this study, in-service diametral creep measurements from CANDU reactors are correlated with α grain dimensions after accounting for the differences in service conditions (operating time, neutron flux, and temperature). The studied pressure tubes cover a population of Zr-2.5Nb CANDU pressure tubes manufactured since 1974 up to 1995 and therefore include a range of manufacturing processes with a corresponding variation of microstructure properties. The α grain dimensions are measured from the images taken using scanning transmission electron microscopy. A key finding of this study is that the α grain aspect ratio, in the cross section perpendicular to the extrusion direction (with the major axis roughly aligned in the hoop direction and minor axis roughly aligned in the wall direction), is a dominant correlate to explain and predict diametral creep.

1.
Krause
M.
and
Bickel
G.
, “
International Database on Heavy Water Reactor Pressure Tube Diametral Creep
” (paper presentation, TopSafe 2017,
Vienna, Austria
, February 12–16,
2017
).
2.
Cheadle
B. A.
,
Coleman
C. E.
, and
Licht
H.
, “
CANDU-PHW Pressure Tubes: Their Manufacture, Inspection, and Properties
,”
Nuclear Technology
57
(
1982
): 413–425.
3.
Bickel
G. A.
and
Griffiths
M.
, “
Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes
,”
Journal of ASTM International
4
, no.
10
(
2007
),
4.
Cheadle
B. A.
, “
Fabrication of Zirconium Alloys into Components for Nuclear Reactors
,” in
Zirconium in the Nuclear Industry: Third International Symposium
, ed.
Howe
A. L.
and
Parry
G. W.
(
West Conshohocken, PA
:
ASTM International
,
1977
), 457–485,
5.
Griffiths
M.
,
Holt
R.A.
,
Li
J.
, and
Saimoto
S.
, “
Micro–Texture Analysis of Zr–2.5Nb Pressure Tubes
,”
Microstructural Science
26
(
1999
): 293–302.
6.
Walters
L.
,
Bickel
G. A.
, and
Griffiths
M.
, “
The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr-2.5Nb Pressure Tubing
,” in
Zirconium in the Nuclear Industry: 17th International Symposium
, ed.
Comstock
R.
and
Barberis
P.
(
West Conshohocken, PA
:
ASTM International
,
2015
), 693–725,
7.
Griffiths
M.
,
Bickel
G. A.
,
DeAbreu
R.
, and
Li
W.
, “
Irradiation Creep of Zr-Alloys
,” in
Mechanical and Creep Behavior of Advanced Materials
, ed.
Charit
I.
,
Zhu
Y.T.
,
Maloy
S. A.
, and
Liaw
P. K.
(
New York, NY
:
Springer
,
2017
), 165–182.
8.
Judge
C. D.
,
Li
W.
,
Mayhew
C.
,
Buyers
A.
, and
Bickel
G. A.
, “
Adopting Transmission Kikuchi Diffraction to Characterize Grain Structure and Texture of Zr-2.5Nb CANDU Pressure Tubes
,”
CNL Nuclear Review
7
(
2018
): 119–125,
9.
Hovington
P.
,
Pinard
P. T.
,
Lagacé
M.
,
Rodrigue
L.
,
Gauvin
R.
, and
Trudeau
M. L.
, “
Towards a More Comprehensive Microstructural Analysis of Zr–2.5Nb Pressure Tubing Using Image Analysis and Electron Backscattered Diffraction (EBSD)
,”
Journal of Nuclear Materials
393
(
2009
): 162–174.
10.
Lagacé
M.
,
Rodrigue
L.
,
Hovington
P.
, and
Trudeau
M.
, “
Extracting Quantitative Data from Partly Revealed Anisotropic Microstructures as Applied to Zirconium Tubes
,”
JOM
60
(
2008
): 17–21,
11.
Bickel
G. A.
,
Griffiths
M.
,
Chaput
H.
,
Buyers
A.
, and
Coleman
C. E.
, “
Modeling Irradiation Damage in Zr-2.5Nb and Its Effects on Delayed Hydride Cracking Growth Rate
,” in
Zirconium in the Nuclear Industry: 17th International Symposium
, ed.
Comstock
R.
and
Barberis
P.
(
West Conshohocken, PA
:
ASTM International
,
2015
), 800–829,
12.
Kearns
J. J.
, Thermal Expansion and Preferred Orientation in Zircaloy, Report WAPD-TM (West Mifflin, PA:
Bettis Atomic Power Laboratory
,
1965
).
13.
Bickel
G. A.
,
Walters
L.
, and
Griffiths
M.
, “
Improved Zr–2.5Nb Pressure Tubing for Future HW Reactors
” (paper presentation, Proceedings of the International Conference Future of HWRs,
Ottawa, Canada
, October 2–5,
2011
).
14.
Jyrkama
M. I.
,
Bickel
G. A.
, and
Pandey
M. D.
, “
Statistical Analysis and Modelling of In Reactor Diametral Creep of Zr-2.5Nb Pressure Tubes
,”
Nuclear Engineering and Design
300
(
2016
): 241–248.
15.
Bickel
G. A.
and
Griffiths
M.
, “
Manufacturing Variability and Deformation for Zr-2.5Nb Pressure Tubes
,”
Journal of Nuclear Materials
383
(
2008
): 9–13.
16.
Adamson
R. B.
,
Coleman
C. E.
, and
Griffiths
M.
, “
Irradiation Creep and Growth of Zirconium Alloys: A Critical Review
,”
Journal of Nuclear Materials
521
(
2019
): 167–244.
17.
Heald
P. T.
and
Speight
M. V.
, “
The Influence of Cascade Damage on Irradiation Creep and Swelling
,”
Journal of Nuclear Materials
64
(
1977
): 139–144.
This content is only available via PDF.
You do not currently have access to this chapter.
Close Modal

or Create an Account

Close Modal
Close Modal