Skip to Main Content
Skip Nav Destination
ASTM Selected Technical Papers
Effects of Radiation on Materials: 15th International SymposiumAvailable to Purchase
By
RE Stoller
RE Stoller
1
Oak Ridge National Laboratory
,
Oak Ridge, Tennessee
;
chairman and editor
Search for other works by this author on:
AS Kumar
AS Kumar
2
University of Missouri-Rolla
,
Rolla, Missouri
;
cochairman and editor
Search for other works by this author on:
DS Gelles
DS Gelles
3
Battelle Pacific Northwest Laboratory
,
Richland, Washington
;
cochairman and editor
Search for other works by this author on:
ISBN-10:
0-8031-1477-X
ISBN:
978-0-8031-1477-7
No. of Pages:
1339
Publisher:
ASTM International
Publication date:
1992

The reactor pressure vessel of a pressurized water reactor can be embrittled by neutron irradiation from the core It has been recognized for many years that copper plays a significant role in the embrittlement process and more recently that copper precipitates pin dislocations In developing fundamental understanding and mechanistic models to predict embrittlement, it is important to identify the microscopic mechanisms underlying this phenomena Although considerable progress has been made recently on characterizing the irradiation-produced microstructure, relatively little is known about the nature, morphology, and composition of the copper precipitates or the atomic processes whereby they pin dislocations The purpose of this paper is to discuss recent results from experimental studies and computer modelling of the properties of the copper precipitates formed after irradiating or thermally aging model Fe-Cu and Fe-Cu-Ni alloys.

Results will be presented from transmission electron microscopy (TEM), atom probe field-ion microscopy (AP/FIM), small angle neutron scattering (SANS), and extended X-ray absorption fine structure analysis (EXAFS) on the size dependence of the nature, composition, and internal structure of these precipitates A particularly interesting feature of this is the transformation in thermally aged material from a body-centered cubic (bcc) lattice to a face-centered cubic (fee) lattice at sizes above approximately 5 nm Considerable insight into the properties of bcc copper has been obtained from a molecular dynamics simulation of a block of copper atoms lying on a (metastable) bcc lattice The lattice mismatch with the host iron lattice, the misfit pressure, the elastic moduli, in particular the shear modulus, and the transformation from bcc to fee have been simulated The interaction of dislocations with such a metastable precipitate will also be described Finally, the insight these studies give into the observed macroscopic hardness increase after irradiation or thermal aging will be discussed.

1.
Buswell
,
J. T.
and
Brock
,
J. M.
, TPRD/B/0922/R87,
CEGB Report
,
Central Electricity Generating Board
, UK,
1987
.
2.
Phythian
,
W. J.
and
English
,
C. A.
, AERE-R-13632,
UK Atomic Energy Authority
, Harwell, U K,
1990
.
3.
Worrall
,
G. M.
,
Buswell
,
J. T.
,
English
,
C. A.
,
Hetherington
,
M. G.
, and
Smith
,
G. W. D.
,
Journal of Nuclear Materials
, Vol.
148
,
1987
, p. 107.
4.
Miller
,
M. K.
and
Burke
,
M. G.
,
Proceedings ofthe 3rd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactor
,
The Metallurgical Society
,
1988
, p. 141.
5.
Beaven
,
P. A.
,
Fnsius
,
F.
,
Kampmann
,
R.
, and
Wagner
,
R.
,
Proceedings of the 2nd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors
,
1986
, p. 400.
6.
Lucas
,
G. E.
and
Odette
,
G. R.
,
Proceedings of the 2nd International Symposium on Environmental Degradation of Materials m Nuclear Power Systems—Water Reactors American Nuclear Society
,
1986
, p. 345.
7.
Buswell
,
J. T.
,
Little
,
E. A.
,
Jones
,
R. B.
, and
Sinclair
,
R. N.
,
Proceedings of the 2nd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems— Water Reactors Amencan Nuclear Society
,
1986
, p 139.
8.
Russell
,
K. C.
and
Brown
,
L. M.
,
Acta Metallurgica
, Vol.
20
,
1972
, p. 969.
9.
Odette
,
G. R.
and
Lucas
,
G. E.
,
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels An International Review (2nd Volume)
, ASTM STP 909,
Amencan Society for Testing and Materials
,
Philadelphia
,
1986
, p. 206.
10.
Fisher
,
S. B.
and
Buswell
,
J. T.
,
International Journal of Pressure Vessels and Piping
 0308-0161, Vol.
27
,
1987
, p. 91.
11.
Buswell
,
J. T.
,
English
,
C. A.
,
Hethenngton
,
M. H.
,
Phythian
,
W. J.
,
Smith
,
G. D. W.
, and
Worrall
,
G. M.
,
14th International Symposium on Effects of Radiation on Materials
, ASTM STP 1046,
American Society for Testing and Materials
,
Philadelphia
, p. 127.
12.
Ashby
,
M. F.
and
Brown
,
L. M.
,
Philosophical Magazine
 1478-6435, Vol.
8
, p. 1083.
13.
Eyre
,
B. L.
,
Maher
,
D. M.
and
Pemn
,
R. C.
,
Journal of Physics F: Metal Physics
, Vol.
7
,
1977
, p. 1359.
14.
Phythian
,
W. J.
,
Eyre
,
B. L.
,
Bacon
,
D. J.
, and
English
,
C. A.
,
Philosophical Magazine
 1478-6435, Vol.
55
,
1987
, p. 757.
15.
Hirsch
,
P. B.
,
Howie
,
A.
,
Nicholson
,
R. B.
,
Pashley
,
D. W.
, and
Whelan
,
M. J.
,
Electron Microscopy of Thin Crystals
,
Butterworths
,
Sevenoaks, UK
,
1965
.
16.
Finnis
,
M. W.
and
Barker
,
A. H.
, AERE-R-8824,
U. K. Atomic Energy Association
, Harwell, U K,
1983
.
17.
Finns
,
M. W.
, AERE-R-13182,
U. K. Atomic Energy Association
, Harwell, U K,
1988
.
18.
Ackland
,
G. J.
,
Finnis
,
M. W.
,
Tichy
,
G.
, and
Vitek
,
V.
,
1987
,
Philosophical Magazine
 1478-6435, Vol.
56
,
1987
, p. 735.
19.
Wada
,
H.
,
Houbaert
,
Y.
,
Penning
,
J.
, and
Dilewijns
,
J.
, presented at
Copper in Iron and Steel
, Luxemburg,
1984
,
Copper Research and Development Association
,
U K
.
This content is only available via PDF.
You do not currently have access to this chapter.

or Create an Account

Close Modal
Close Modal