Abstract

The rate of delayed hydride cracking (DHC) has been measured in Zircaloy-4 fuel cladding in several metallurgical conditions using the pin-loading tension technique. In light water reactor (LWR) cladding in the cold-worked and cold-worked and stress-relieved conditions, the cracking rate followed Arrhenius behavior up to about 280 °C, but at higher temperatures the rate declined with no cracking above 300°C. Non-LWR cladding appeared to behave in the same manner. In LWR cladding in the recrystallized condition, the cracking rate was highly variable because it depended on KI within the test range up to 25 MPa√m, whereas in the other LWR claddings, cracking rate was independent of KI, indicating that KIH was below 11 MPa√m. The main role of microstructure was to control the material strength; the cracking rate increased as the strength increased. Although all the claddings had a radial texture, it did not protect the cladding from DHC. The DHC fracture surface consisted of flat broken hydrides, often in arcs, but no striations were observed, except in one specimen subjected to thermal cycles.

References

1.
Coleman
,
C. E.
, “
Cracking of Hydride-Forming Metals and Alloys
,”
Comprehensive Structural Integrity
, Vol.
6
,
I.
Milne
,
R. O.
Ritchie
, and
B.
Karihaloo
, Eds.,
Elsevier
,
Kidlington, Oxford, UK
,
2003
, Chap. 6.03, pp.
103
161
.
2.
Cheadle
,
B. A.
,
Coleman
,
C. E.
, and
Ambler
,
J. F. R.
, “
Prevention of Delayed Hydride Cracking in Zirconium Alloys
,”
Zirconium in the Nuclear Industry—Seventh International Symposium, ASTM STP 939
, Strasbourg, France, June 24–27, 1985,
R. B.
Adamson
and
L. F. P.
Van Swam
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1987
, pp.
224
240
.
3.
Smith
,
R. R.
and
Eadie
,
R. L.
, “
High Temperature Limit for Delayed Hydride Cracking
,”
Scr. Metall.
 0036-9748, Vol.
22
,
1988
, pp.
833
836
. https://doi.org/10.1016/S0036-9748(88)80058-9
4.
Simpson
,
C. J.
and
Ells
,
C. E.
, “
Delayed Hydrogen Embrittlement in Zr–2.5 wt%Nb
,”
J. Nucl. Mater.
 0022-3115, Vol.
52
,
1974
, pp.
289
295
. https://doi.org/10.1016/0022-3115(74)90174-3
5.
Perryman
,
E. C. W.
, “
Pickering Pressure Tube Cracking Experience
,”
Nucl. Energy
 0140-4067, Vol.
17
,
1978
, pp.
95
105
.
6.
Platonov
,
P. A.
,
Ryazantseva
,
A. V.
,
Saenko
,
G. P.
,
Knizhnikov
,
Y. N.
, and
Viktorov
,
V. F.
The Study of Cause of Cracking in Zirconium Alloy Channel Tubes
,”
Poster Paper at ASTM Zirconium in the Nuclear Industry—Eighth International Symposium
, San Diego, CA, June 19–23,
1988
,
ASTM
,
Philadelphia, PA
,
1988
, available as AECL Report RC-87.
7.
Jonsson
,
A.
,
Hallstadius
,
L.
,
Grapengiesser
,
B.
, and
Lysell
,
G.
, “
Failure of a Barrier Rod in Oskarshamn-3
,”
Fuel for the ‘90’s, International Topical Meeting on LWR Fuel Performance
, Avignon, France, April 21–24, 1991,
American Nuclear Society
,
La Grange Park, IL
and European Nuclear Society, Brussels, Belgium,
1991
, pp.
371
377
.
8.
Schrire
,
D.
,
Grapengiesser
,
B.
,
Hallstadius
,
L.
,
Lundholm
,
I.
,
Lysell
,
G.
,
Frenning
,
G.
,
Ronnberg
,
G.
, and
Jonsson
,
A.
, “
Secondary Defect Behaviour in ABB BWR Fuel
,”
International Topical Meeting on Light Water Reactor Fuel Performance
, West Palm Beach, April 17–21, 1984,
American Nuclear Society
,
La Grange Park, IL
,
1994
, pp.
398
409
.
9.
Armijo
,
J. S.
, “
Performance of Failed BWR Fuel
,”
International Topical Meeting on Light Water Reactor Fuel Performance
, San Diego, CA, June 19–23, 1988,
American Nuclear Society
,
La Grange Park, IL
,
1994
, pp.
410
422
.
10.
Clayton
,
J. C.
, “
Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods
,”
Zirconium in the Nuclear Industry—Eighth International Symposium, ASTM STP 1023
,
L. F. P.
Van Swam
and
C. M.
Eucken
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1989
, pp.
266
288
.
11.
Lysell
,
G.
and
Grigoriev
,
V.
, “
Characteristics of Axial Splits in Failed BWR Fuel Rods
,”
Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors
, Newport Beach, CA, August 1–5, 1999,
The Minerals, Metals and Materials Society
,
Warrendale, PA
,
1999
, pp.
1169
1175
.
12.
Efsing
,
P.
and
Pettersson
,
K.
, “
Delayed Hydride Cracking in Irradiated Zircaloy Cladding
,”
Zirconium in the Nuclear Industry—12th International Symposium, ASTM STP 1354
, Toronto, Canada, June 15–18, 1998,
G. P.
Sabol
and
G. D.
Moan
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2000
, pp.
340
355
.
13.
Edsinger
,
K.
,
Davies
,
J. H.
, and
Adamson
,
R. B.
, “
Degraded Fuel Cladding Fractography and Fracture Behavior
,”
Zirconium in the Nuclear Industry—12th International Symposium, ASTM STP 1354
, Toronto, Canada, June 15–18, 1998,
G. P.
Sabol
and
G. D.
Moan
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2000
, pp.
316
339
.
14.
Edsinger
,
K.
, “
A Review of Fuel Degradation in BWRs
,”
Int. Topical Meeting on Light Water Reactor Fuel Performance
, Park City, April 10–13, 2000,
American Nuclear Society
,
La Grange Park, IL
,
2000
, pp.
162
179
.
15.
Shimada
,
S.
,
Etoh
,
E.
,
Hayashi
,
H.
, and
Tukuta
,
Y.
, “
A Metallographic and Fractographic Study of Outside-In Cracking Caused by Power Ramp Tests
,”
J. Nucl. Mater.
 0022-3115, Vol.
327
,
2004
, pp.
97
113
. https://doi.org/10.1016/j.jnucmat.2004.01.022
16.
Sakamoto
,
K.
,
Nakatsuka
,
M.
, and
Higuchi
,
T.
, “
Simulation of Cracking During Outside-In Type Failure of High Burn-Up Fuel Cladding Tubes
,”
Water Reactor Fuel Performance Meeting
, Seoul, Korea, October 19–23, 2008,
Korean Nuclear Society
,
Seoul, Korea
,
2008
, Paper 8009.
17.
Ogata
,
K.
,
Baba
,
T.
,
Kamimura
,
K.
,
Etoh
,
Y.
, and
Ito
,
K.
, “
Separate Effects of Factors Affecting Outside-In Cracking of High Burnup Fuel Cladding
,”
Water Reactor Fuel Performance Meeting
, Seoul, Korea, October 19–23, 2008,
Korean Nuclear Society
,
Seoul, Korea
,
2008
, Paper 8130.
18.
Unnikrishnan
,
K.
,
Mishra
,
P.
,
Jathar
,
V. P.
,
Kumar
,
S.
,
Sahoo
,
K. C.
, and
Anantharaman
,
S.
, “
Observation of Delayed Hydride Cracking in PHWR Fuel Assembly
,”
Tenth CNS International Conference on CANDU Fuel
, Toronto, Canada, October 5–8, 2008,
Canadian Nuclear Society
,
Toronto, ON, Canada
,
2008
.
19.
Coleman
,
C. E.
and
Inozemtsev
,
V. V.
, “
Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr–2.5Nb alloys—An IAEA Coordinated Research Project
,”
J. ASTM Int.
 1546-962X, Vol.
5
,
2008
, paper ID JAI101091. https://doi.org/10.1520/JAI101091
20.
Efsing
,
P.
and
Pettersson
,
K.
, “
The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2
,”
Zirconium in the Nuclear Industry—Eleventh International Symposium, ASTM STP 1295
, Garmisch-Partenkirchen, Germany, September 11–14, 1995,
E. R.
Bradley
and
G. P.
Sabol
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1996
, pp.
394
404
.
21.
Grigoriev
,
V.
and
Jakobsson
,
R.
, “
Delayed Hydrogen Cracking Velocity and J-Integral Measurements on Irradiated BWR Cladding
,”
J. ASTM Int.
 1546-962X, Vol.
2
,
2005
, paper ID JAI12434. https://doi.org/10.1520/JAI12434
22.
Grigoriev
,
V.
,
Josefsson
,
B.
,
Lind
,
A.
, and
Rosborg
,
B.
, “
A Pin-Loading Tension Test for Evaluation of Thin-Walled Tubular Materials
,”
Scr. Metall. Mater.
 0956-716X, Vol.
33
, No.
1
,
1995
, pp.
109
114
. https://doi.org/10.1016/0956-716X(95)00110-H
23.
Grigoriev
,
V.
,
Josefsson
,
B.
, and
Rosborg
,
B.
, “
Fracture Toughness of Zircaloy Cladding Tubes
,”
Zirconium in the Nuclear Industry—Eleventh International Symposium, ASTM STP 1295
, Garmisch-Partenkirchen, Germany, September 11–14, 1995,
E. R.
Bradley
and
G. P.
Sabol
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1996
, pp.
431
447
.
24.
Yagnik
,
S. K.
,
Ramasubramanian
,
N.
,
Grigoriev
,
V.
,
Sainte-Catherine
,
C.
,
Bertsch
,
J.
,
Adamson
,
R.
,
Kuo
,
R.-C.
,
Mahmood
,
S. T.
,
Fukuda
,
T.
,
Efsing
,
P.
, and
Oberländer
,
B. C.
, “
Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing
,”
J. ASTM Int.
 1546-962X, Vol.
5
,
2008
, paper ID JAI101140. https://doi.org/10.1520/JAI101140
25.
Coleman
,
C.
,
Grigoriev
,
V.
,
Inozemtsev
,
V.
,
Markelov
,
V.
,
Roth
,
M.
,
Makarevicius
,
V.
,
Kim
,
Y. S.
,
Kanwar
,
L. A.
,
Chakravartty
,
J. K.
,
Mizrahi
,
R.
, and
Lalgudi
,
R.
, “
Delayed Hydride Cracking in Zircaloy Fuel Cladding—An IAEA Coordinated Research Programme
,”
Nucl. Eng. Technol.: Int. J. Korean Nucl. Soc.
, Vol.
41
,
2009
, pp.
171
178
.
26.
Grigoriev
,
V.
and
Jakobsson
,
R.
, “
DHC Axial Crack Velocity Measurements in Zirconium Alloy Fuel Cladding
,” STUDSVIK/N-05/281, Studsvik Nuclear AB,
2005
, ISBN 91-7010-377-1.
27.
Roth
,
M.
, Compliance measurements based on Ref , INR, June 23,
2009
.
28.
Huang
,
F. H.
and
Mills
,
W. J.
, “
Delayed Hydride Cracking Behavior for Zircaloy-2 Tubing
,”
Metall. Trans. A
 0360-2133, Vol.
22A
,
1991
, pp.
2049
2060
.
29.
Puls
,
M. P.
,
Simpson
,
L. A.
, and
Dutton
,
R.
, “
Hydride-induced crack growth in zirconium alloys
,” AECL Report AECL-7392, Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada,
1982
.
30.
Coleman
,
C. E.
, “
Effect of Texture on Hydride Reorientation and Delayed Hydrogen Cracking in Cold-Worked Zr–2.5Nb
,”
Zirconium in the Nuclear Industry—Fifth International Conference, ASTM STP 754
, Boston. MA, August 4–7, 1980,
D. G.
Franklin
, Ed.,
ASTM International
,
West Conshohocken, PA
,
1982
, pp.
393
411
.
31.
Coleman
,
C. E.
,
Cheadle
,
B. A.
,
Cann
,
C. D.
, and
Theaker
,
J. R.
, “
Development of Pressure Tubes with Service Life Greater Than 30 Years
,” Garmisch-Partenkirchen, Germany, September 11–14, 1995,
Zirconium in the Nuclear Industry—Eleventh International Symposium, ASTM STP 1295
,
E. R.
Bradley
and
G. P.
Sabol
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1996
, pp.
884
898
.
32.
Kim
,
S. S.
and
Kim
,
Y. S.
, “
KIH in Radial Textured Zr–2.5%Nb Pressure Tube
,”
J. Nucl. Mater.
 0022-3115, Vol.
279
,
2000
, pp.
286
292
. https://doi.org/10.1016/S0022-3115(99)00284-6
33.
Aomi
,
M.
,
Baba
,
T.
,
Miyashita
,
T.
,
Kamimura
,
K.
,
Yasuda
,
T.
,
Shinohara
,
Y.
, and
Takeda
,
T.
, “
Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage
,”
J. ASTM Int.
 1546-962X, Vol.
5
,
2008
, paper ID JAI101262. https://doi.org/10.1520/JAI101262
34.
Sagat
,
S.
and
Puls
,
M.P.
, “
Temperature Limit for Delayed Hydride Cracking in Zr–2.5Nb Alloys
,”
17th Inter. Conf. Structural Mechanics in Reactor Technology
, Prague, Czech Republic, August 17–22
2003
,
International Association for Structural Mechanics in Reactor Technology
,
Berlin, Germany
,
2003
, Paper G06-4.
35.
Resta Levi
,
M.
and
Puls
,
M. P.
, “
DHC Behaviour of Irradiated Zr–2.5Nb Pressure Tubes up to 365°C
,”
18th Inter. Conf. on Structural Mechanics in Reactor Technology
, Beijing, China, August 7–12
2005
,
International Association for Structural Mechanics in Reactor Technology
,
Berlin, Germany
2005
, Paper G10-3.
36.
Mahmood
,
S. T.
,
Farkas
,
D. M.
,
Adamson
,
R. B.
, and
Etoh
,
Y.
, “
Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate
,”
Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354
, Toronto, Canada, June 15–18, 1998,
G. P.
Sabol
and
G. D.
Moan
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2000
, pp.
139
169
.
37.
Ambler
,
J. F. R.
, “
Effect of Direction of Approach to Temperature on the Delayed Hydrogen Cracking Behavior of Cold-Worked Zr–2.5Nb
,”
Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP 824
, Vancouver, Canada, June 28–July 1, 1982,
D. G.
Franklin
and
R. B.
Adamson
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1984
, pp.
653
674
.
38.
Sagat
,
S.
,
Chow
,
C. K.
,
Puls
,
M. P.
, and
Coleman
,
C. E.
, “
Delayed Hydride Cracking in Zirconium Alloys in a Temperature Gradient
,”
J. Nucl. Mater.
 0022-3115, Vol.
279
,
2000
, pp.
107
117
. https://doi.org/10.1016/S0022-3115(99)00265-2
39.
Sakamoto
,
K.
,
Nakatsuka
,
M.
,
Higuchi
,
T.
, and
Ito
,
K.
, “
Role of Radial Temperature Gradient in Outside-In Type Failure of High Burn-Up Fuel Cladding Tubes During Power Ramp Tests
,”
Proc. Top Fuel 2009
, Paris, France, September 6–10, 2009,
French Nuclear Energy Society
,
Paris
,
2009
, Paper 2076.
This content is only available via PDF.
You do not currently have access to this content.