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ASTM Selected Technical Papers
Application of Accelerated Corrosion Tests to Service Life Prediction of Materials
By
G Cragnolino
G Cragnolino
1
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute
,
San Antonio, TX
;
symposium chairmen and editors
.
Search for other works by this author on:
N Sridhar
N Sridhar
1
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute
,
San Antonio, TX
;
symposium chairmen and editors
.
Search for other works by this author on:
ISBN-10:
0-8031-1853-8
ISBN:
978-0-8031-1853-9
No. of Pages:
401
Publisher:
ASTM International
Publication date:
1994

A disposal system for high-level and long-lived radioactive waste should provide for adequate isolation of radionuclides from the bio-sphere.

During the work of finding such a system, and in demonstrating its long-term isolation, certain unprecedented requirements become apparent: the disposal system must function over very long times without any need for maintenance or repair. Furthermore, no experience from operation can be made available for the analysis, and there will be no results from tests with durations comparable in magnitude to the life-time of the facility.

In the systems studied in Sweden and Finland, copper containers are deposited in crystalline bedrock with bentonite as a backfill. The groundwater is reducing and the flow is very low due to the low permeability of the bentonite clay and of the rock near the deposition hole.

The chemical durability of a container in such a disposal system will depend primarily on three factors: the mechanical tensile stresses in the container, the chemical environment, and the copper material itself. The tensile stresses depend on manufacturing factors as well as external forces. The chemical environment will depend on the composition of the groundwater, theibentonite clay and possibly also phenomena that might take place in the vicinity of the container. The copper material can corrode primarily by oxidation or sulphidation. If the salt concentration is high (and a reducible specie is available), copper may also react by forming chloride complexes.

If the copper container has thick walls, penetration by general corrosion will take considerable time. It is nevertheless of interest to study general corrosion since - at least under certain conditions - it will give rise to a protective and passivating surface layer. Such a layer may be of significance when the possibilities of localized corrosion and stress corrosion cracking are to be evaluated. It is pointed out that the development of localized corrosion is strongly dependent on the specific chemistry. Concern is expressed regarding certain treacherous aspects of stress corrosion cracking. Areas of research that may be fertile to pursue have also been identified.

A point is made that the safety analyses and scenarios should include both probable and less probable developments. Examples are given of the latter type.

A suggestion is made that samples of the container and of container material be left in the repository to enable evaluation and thus to facilitate improvements that future generations might wish to make.

1.
Final storage of spent nuclear fuel - KBS-3
,
Swedish Nuclear Fuel Supply Company
(now SKB),
05
1983
.
2.
SKI Projekt-90, SKI Technical Report 91:23, August 1991.
3.
SKB-91.
Slutlig förvaring av använt kärnbränsle. Berggrundens betv-delse för säkerheten, [english translation of the title: “SKB-91.Final storage of spent nuclear fuel. The significance of the bed-rock for the safety,”]
,
Swedish Nuclear Fuel and Waste Management Company
, May, 1992. To be published in English.
4.
Evaluation of SKB R&D Programme 89
,
The National Board for Spent Nuclear Fuel
, March, 1990.
5.
Andersson
,
J.
, editor,
The joint SKI/SKB scenario development project
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12
1989
.
6.
Fifth Report to the U.S. Congress and the U.S. Secretary of Energy,
the United States Nuclear Waste Technical Review Board
,
06
1992
.
7.
McEwen
,
T.
and
de Marsily
,
G.
,
The potential significance of per-mafrost to the Behaviour of a Deep Radioactive Waste Repository
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8.
Ahlbom
,
K.
,
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,
T.
and
Ericsson
L., 0.
,
SKB/TVO ice age scenario
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06
1991
.
9.
Manakatala
,
H., K.
and
Interrante
,
C., G.
,
Technical considerations for evaluating substantially complete containment of high-level waste within the waste package
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12
1990
.
10.
Manaktala
,
H.
,
Wu
,
Y.
,
Nair
,
P.
,
Interrante
,
C.
and
Bunting
,
J.
,
Technical considerations for evaluating substantially complete containment of high-level waste
,
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, Vol
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Rajainmaki
,
H.
,
Nieminen
,
M.
and
Laakso
,
L.
,
Production methods and costs of oxygen free copper canisters for nuclear waste disposal
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06
1991
, also published as Nuclear Waste Commission of Finnish Power Companies, Report YJT-91-17,
08
1991
.
12.
Werme
,
L.
,
Near-field performance of the advanced cold process canister
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09
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, also published as Nuclear Waste Commission of Finnish Power Companies, Report YJT-90-20,
12
1990
.
13.
Auerkari
,
P.
,
Leinonen
,
H.
and
Sandlin
,
S.
,
Creep of OFHC and silver copper at simulated final repository canister-service conditions
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09
1991
, also published as Nuclear Waste Commission of Finnish Power Companies, Report YJT-91-16,
07
1991
.
14.
Henderson
,
P., J.
,
österberg
,
J-O
, and
Ivarsson
,
B.
,
Low temperature creep of copper intended for nuclear waste containers
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03
1992
.
15.
Auerkari
,
P.
and
Sandlin
,
S.
,
Long term creep strength of silver alloyed copper
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12
1988
.
16.
Pedersen
,
K.
,
Potential effects of bacteria on radionuclide transport from a Swedish high level nuclear waste repository
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01
1990
.
17.
Lagerblad
,
B.
,
Chemistry and genesis of deep around waters in crystalline bedrock
,
SKN/SKI
to be published.
18.
Vallander
,
P.
and
Eurenius
,
J.
,
Impact of a repository on permafrost development during glaciation advance
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12
1991
.
19.
Lindbom
,
B.
and
Boghammar
,
A.
,
Exploratory calculations concerning the influence of alacviation and permafrost on the aroundwater flow system, and an initaial study of permafrost influences at the Finnsjön site — an SKB-91 study
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12
1991
.
20.
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, System-nummer 60,
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21.
Copper, Part two,
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Copper
,
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23.
Gerhartz
,
W.
, editor.
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, pp 471–593.
24.
Leidheiser
,
H
,
The corrosion of copper, tin, and their alloys,part one, Corrosion of Copper and its alloys
,
John Wiley and Sons,Inc
,
1970
.
25.
Pugh
,
E., N.
,
Craig
,
J., V.
and
Sedriks
,
A., J.
,
The stress corrosion cracking of copper, silver, and gold alloys
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The Ohio State University
,
USA
, September 11–15, 1967.
26.
Benjamin
,
L., A.
,
Hardie
,
D.
and
Parkins
,
R., N.
,
Investigation of the stress corrosion cracking of pure copper
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04
1983
.
27.
The Swedish Corrosion Research Institute and its reference group
,
Corrosion resistance of a copper canister for spent nuclear fuel
, SKB Technical Report 83-24,
04
1993
.
28.
Amcoff
,
ö.
and
Holényi
K.
,
Stability of metallic copper in the near surface environment
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03
1992
.
29.
Marcos
,
N
,
Native copper as a natural analogue for copper canisters
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12
1989
.
30.
Aaltonen
,
P.
,
Corrosion of pure OFHC-copper in simulated repository conditions
, Part I, Nuclear Waste Commission of Finnish Power Companies, Report YJT-88-09,
06
1988
.
31.
Aaltonen
,
P.
,
Corrosion of pure OFHC-copper in simulated repository conditions
, Part II, Nuclear Waste Commission of Finnish Power Companies, Report YJT-90-07,
04
1990
.
32.
Beavers
,
J., A.
and
Thompson
,
N. G.
,
Environmental effects on corrosion in the tuff repository
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02
1990
.
33.
Farmer
,
J., C.
,
McCright
,
R., D.
and
Kass
,
J., N.
,
Survey of degradation modes of candidate materials for high-level radioactive waste disposal containers, overview
,
Lawrence Livermore National Laboratory
on commission by US DOE, UCID--21362,
06
1988
.
34.
Gdowski
,
G., E.
and
Bullen
,
D, B
,
Survey of degradation modes of candidate materials for high-level radioactive waste disposal containers, volume 2 oxidation and corrosion
,
Lawrence Livermore National Laboratory
on commission by US DOE, UCID--21362,
08
1988
.
35.
Farmer
,
J., C.
,
Van Konynenburg
,
R., A.
and
McCright
,
R., D.
,
Survey of degradation modes of candidate materials for high-level radioactive waste disposal containers, volume 4 stress corrosion of copper-based alloys
,
Lawrence Livermore National Laboratory
on commission by US DOE, UCID--21362,
05
1988
.
36.
Farmer
,
J., C.
,
Van Konynenburg
,
R., A.
,
McCright
,
R., D.
and
Gdowski
,
G., E.
,
Survey of degradation modes of candidate materials for high-level radioactive waste disposal containers, volume 5 localized corrosion of copper-based alloys
,
Lawrence Livermore National Laboratory
on commission by US DOE, UCID--21362,
05
1988
.
37.
Maiya
,
P., S.
,
A review of degradation behavior of container materials for disposal of high-level nuclear waste in tuff and alternative repository environments
, Argonne National Laboratory, ANL--89/14,
06
1989
.
38.
Kass
,
J.
,
Evaluation of copper, aluminium bronze, and copper-nickel for the Yucca mountain project
,
Lawrence Livermore National Laboratory
, Corrosion of nuclear fuel waste containers, proceedings of a workshop in Winnipeg,
Canada
, February 9–10, 1988.
39.
Farmer
,
J., C.
,
Gdowski
,
G., E.
,
McCright
,
R., D.
and
Ahluwahlia
,
H., S.
,
Corrosion models for performance assessment of high-level radioactive waste containers
,
Nuclear Engineering and Design
 0029-5493, Vol
129
,
1991
, pp 57–88.
40.
McNeil
,
M., B.
and
Little
,
B., J.
,
Corrosion products and mechanisms in long-term corrosion of copper
, Scientific Basis for Nuclear Waste Management XIV, Boston, USA, November 26–29, 1990.
41.
Reed
,
D., T.
and
Van Konynenburg
,
R., A.
,
Corrosion of copper-based materials in irradiated moist air systems
, Scientific Basis for Nuclear Waste Management XIV, Boston, USA, November 26–29, 1990.
42.
Manaktala
,
H., K.
,
Degradation modes in candidate copper-based materials for high-level radwaste canisters
, Corrosion 90,
Las Vegas, USA
, April 23–27, 1990.
43.
Shoesmith
,
D., W.
, editor,
Corrosion of nuclear fuel waste containers
, Proceedings of a workshop held in Winnipeg,
Canada
, February 9–10, 1988.
44.
King
,
F.
and
LeNeveu
,
D.
,
Prediction of the lifetimes of copper nuclear waste containers
, Nuclear waste packaging, Focus'91, Las Vegas, USA, September 29 – October 2, 1991.
45.
King
,
F.
and
Litke
,
C.
,
The corrosion of copper in NaCl solution and under simulated disposal conditions
, Scientific basis for nuclear waste management XII, Pittsburgh, USA,
1989
, pp 403–409.
46.
King
,
F.
and
Litke
,
C.
,
Electrochemical behaviour of copper in aerated m mol per litre NaCl at room temperature
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1989
.
47.
Hultqvist
,
G.
,
Hydrogen evolution in corrosion of copper in pure water
,
Corrosion Science
 0010-938X, Vol
26
, No
2
, pp173–177,
1986
.
48.
Hultqvist
,
G.
,
Chuah
,
G., K.
and
Tan
,
K., L.
,
Comments on hydrogen evolution from the corrosion of pure copper
,
Corrosion Science
 0010-938X, Vol
29
, No
11/12
, pp 1371–1377,
1989
.
49.
Hultqvist
,
G.
,
Chuah
,
G., K.
and
Tan
,
K., L.
,
A SIMS study of reactions in the metal-oxvgen-hvdrogen-water system
,
Corrosion Science
 0010-938X, Vol
31
, pp 149–154,
1990
.
50.
Simpson
,
J., P.
and
Schenk
,
R.
,
Hydrogen evolution from corrosion of pure copper
,
Corrosion Science
 0010-938X, Vol
27
, No
12
, pp 1365–1370,
1987
.
51.
Eriksen
,
T., E.
,
Ndalambada
,
P.
and
Grenthe
,
I.
,
On the corrosion of pure copper in pure water
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52.
Handling and final disposal of nuclear waste. Programme for re-search, development and other measures
, SKB R&D Programme 89, September, 1989.
53.
Berger
,
R.
,
University of Uppsala, Institute of Chemistry
, Uppsala, Sweden, private communication.
54.
Grauer
,
R.
,
The reducibilitv of sulphuric acid and sulphate in aqueous solution (translated from German)
, SKB Technical Report 91-39,
07
1990
.
55.
Pedersen
,
K
,
Ekendal
,
S.
and
Arlinger
,
J.
,
Microbes in crystalline bedrock. Assimilation of carbon dioxide and introduced organic compounds by bacterial populations in aroundwater from deep crystalline bedrock at Laxemar and Stripa
, SKB Technical Report 91-56,
12
1991
.
56.
Hwang
,
Y.
and
Pigford
,
T., H.
,
Life of copper canister limited by mass transfer of sulfide
, to be published by the SKI.
57.
Hermansson
,
H-P
, and
Rosborg
,
B.
,
Studsvik Materials AB
, Nyköping,Sweden, private communication.
58.
Pusch
,
R.
,
Final report of the Buffer Mass Test — Volume II: test results
, Stripa Project Technical Report 85-12,
08
1985
.
59.
Wu
,
Y.
and
Nair
,
P.
,
Fast probabilistic performance assessment (FPPA) methodology evaluation
, CNWRA 88-004,
10
1988
.
60.
Ethical aspects on nuclear waste
, some salient points discussed at a seminar on ethical action in the face of uncertainty held by KASAM and SKN in
Stockholm, Sweden
, September 8–9, 1987, SKN report 29.
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