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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry
By
DG Franklin
DG Franklin
1
Program manager
,
Core Materials, Electric Power Research Institute
,
Palo Alto, Calif. 94303
;
coeditor
.
Search for other works by this author on:
RB Adamson
RB Adamson
2
Manager
,
Core Materials Testing and Analysis, General Electric Corp.
,
Pleasanton, Calif. 94566
;
coeditor
.
Search for other works by this author on:
ISBN-10:
0-8031-0270-4
ISBN:
978-0-8031-0270-5
No. of Pages:
858
Publisher:
ASTM International
Publication date:
1984

Mechanical joints between Zircaloy and nickel-bearing alloys, mainly the Zircaloy-4/Inconel-600 combination, were exposed to water at 232 and 271°C to study hydriding of Zircaloy in contact with a dissimilar metal. Accelerated hydriding of the Zircaloy occurred at both temperatures. At 232°C the dissolved hydrogen level of the water was over ten times that at 271°C. At 271°C the initially high hydrogen ingress rate decreased rapidly as exposure time increased and was effectively shut off in about 25 days. Severely hydrided Zircaloy components successfully withstood thermal cycling and mechanical testing. Chromium plating of the nickel-bearing parts was found to be an effective and practical barrier in preventing nickel alloy smearing and accelerated hydriding of Zircaloy.

1.
Warren
,
M. R.
,
Roerbo
,
K.
, and
Adolph
,
E.
,
Journal of Nuclear Materials
 0022-3115, Vol.
58
,
1975
, pp. 185-188.
2.
Johnson
,
A. B.
, Jr.
,
Review of Coatings Corrosion
, Vol.
1
,
1975
, pp. 299-365.
3.
Johnson
,
A. B.
, Jr.
, in
Proceedings
,
4th International Conference on Metallurgical Corrosion, Amsterdam 1969
;
National Association of Corrosion Engineers
,
Houston, Tex.
,
1972
, pp. 168-177.
4.
Wolfe
,
R. A.
,
Bingman
,
F. O.
,
Fischer
,
R. L.
,
LaCerte
,
R. C.
, and
Losco
,
E. F.
, “
Eutectic-Diffusion Bonding of Plate-Type Fuel Elements Containing Ceramic Fuel
,” WAPD-211,
Westinghouse Electric Corp., Bettis Atomic Power Laboratory
,
West Mifflin, Pa.
,
10
1960
.
5.
Connors
,
D. R.
,
Milani
,
S.
,
Fest
,
J. A.
, and
Atherton
,
R.
, “
Design of the Shippingport Light Water Breeder Reactor
,” WAPD-TM-1208,
Westinghouse Electric Corp., Bettis Atomic Power Laboratory
,
West Mifflin, Pa.
,
01
1979
.
6.
Clayton
,
J. C.
, “
Out-of-Pile Accelerated Hydriding of Zircaloy Fasteners
,” WAPD-TM-1426,
Westinghouse Electric Corp., Bettis Atomic Power Laboratory
,
West Mifflin, Pa.
,
10
1979
.
7.
Hyatt
,
B. Z.
, “
Metallographic Standards for Estimating Hydrogen Content of Zircaloy-4 Tubing
,” WAPD-TM-1431,
Westinghouse Electric Corp., Bettis Atomic Power Laboratory
,
West Mifflin, Pa.
,
02
1982
.
8.
Clayton
,
J. C.
, “
Sources of Internal Hydriding in Unirradiated Thoria Fueled Zircaloy Rods
,” WAPD-TM-1272,
Westinghouse Electric Corp., Bettis Atomic Power Laboratory
,
West Mifflin, Pa.
,
02
1979
.
9.
Pement
,
F. W.
, “
Hydrogen Accumulation Rates Within Thick-Walled Tubes of Fe-Cr and Fe-Cr-Ni Alloys During Exposure to High-pH, High-Temperature, Pressurized Water Containing Dissolved Hydrogen
,” WERL-1114-3,
Westinghouse Research Laboratories
,
Pittsburgh, Pa.
,
06
1967
.
10.
Gulbransen
,
E. A.
,
Andrew
,
K. F.
,
Jansson
,
S. A.
, and
Pebler
,
A. R.
, “
Hydrogen Reactions with Alloys of Zr and the Metals V, Cr, Fe, Co, Ni, Cu, Mo, Nb and Sn
,” WERL-3203-10,
Westinghouse Research Laboratories
,
Pittsburgh, Pa.
,
06
1967
.
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