ML19331E255
| ML19331E255 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/03/1980 |
| From: | Andrea Johnson BROOKHAVEN NATIONAL LABORATORY |
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| ML19331E251 | List: |
| References | |
| NUDOCS 8009090487 | |
| Download: ML19331E255 (5) | |
Text
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,:o-cracking.
Sannarone perfomed experiments with several galvanic couples in boMc acid solutions' at 50 to 300*C.(45) Approximately 50 dissimilar metal i
couple 3 were investigated.
The only couples which showed evidence of galvanic corrosion were those involving aluminum, 4340 carbon steel, boronated stainless staal, boral, and nickel-plated 80 Ag-15 In-5 Cd.
Corrosion and baron absorption experiments were perfomed on several metals under irradiation in boric acid solutions (up to 50 ppm 8) at s50 to 60*C. @ )
Pilot plant and laceratory tests also were con eted.
The results s
indicated that carbon steel was not an acceptable material. Some pitting occurred on 6061 aluminum alloy specimens; behavior of 17-4 TH steel was acceptable. Aluminum corrosion was lower in the boric acid solutions than in pure water.
No effects of oxygen at concentrations bc? w 1.6 ppm were observed; tests at higher oxygen concentration were not conducted.
The tests therefore differ frcm boHc acid fuel pool chemistries, due to lower oxygen and boric acid concentrations.
Effects of Radiation en Corrosion Effects of. reactor radiation ") on the corrosion of fuef bundle matarials I
have been charactarized.(,'8)
At reactor primary systen conditions, nuclear radiation has major effects on Zircaloy corrosion in oxygenated coolants, including BWR primary systam chemistry. This results in 15 to 25 um of unifom oxide on high-excesure Zircaloy BWR fuel reds, but with local thick-nesses up to %150 pm. b7)
On PWR Zircaloy-clad reds, oxides on the coolant side are generally 15 to 20 pm at end-of-life.U8) and radiation has only a minor influence on corrosion in low-oxygen watar reactor environments.
This observation applies to both bora'ted and nonborated reactor coolants.UI' Reactor radiation also had minor effects on the corresion of stainiess I
steel and Inconel-600 in a lcw-oxygen reactor coolant.
(*}PMncipally neutren, gan=a and beta radiation, with lesser fluxes of ai;:na, deutarens, etc.
The available evidenca points to fast neutrens as tne pMncipal scurce cf accaleratad in-react::r corresion on the Zircalays.
8000090 63.
6 2
Y In water poci sto age, neutron fluxes (s10 n/cm see through nuclear wasta canisters (49)) are almost certainly negligible from the standpoint of
')
corrosion effects.
Ganna fluxes on fuel rod surfaces are estimated to be 6
S10 R/hr at. reactor shutdown, decaying by 3 to 4 orders of magnitude in four years.
Cowan and Tedman indicate that gama fluxes change the chemical environ-ments at corroding surfaces, in some cases having a pronounced effect on
~
corrosionprocesses.(50)
In oxygen-saturated fuel peal waters, formation of,
H0 will be favored.
In some systems, stainless steel potentials are shifted 22 to more passive values. Sensitized materials siay shift to a potantial regime where the matrix is more passive, but the chromium-depleted grain boundaries
~
remain active, promoting intergranular agack. Cowan and Tedman warn that selection of cleaning solutions must be made carefully to avoid subsequent j
accelerated corrosion under irradittion. This consideration could be important if processes to renove crud from the fuel become desirable.
'There is some evidence that pure gama fluxes may accelerate Zircaloy i
aqueous corrosion in the thin film range at elevated tamperatures, but the preponderance of evidence suggests that gama' fluxes do not significantly
)
influence Zircaloy corrosion at reactor temperatures.(51) Visual observa-tions suggest that gama fluxes also do not have an accelerating influence on corrosion under pool storage conditions,(42) but we are not aware of syste-matic confirmatory data.
The situation is similar for stainless steel, vi:.,
Sck of evidence that gama fluxes either prmote or inhibit corresion, but with minimal detailed investigation of interactions between the gamma fluxes and other pool storage parameters such as water chemistry.
Biolocical Corrosion l
~
Bacteria and other biological species are known to cause corrosion of numerous materials including iron-base aTioys. There does not appear to be evidence that zirconium alloys are susceptible to biological corrosion.
Sc=e algae growth occurs in fuel pools, particularly on concrete walls when water chemistry is not carefully controlled. Algae growth has been a minor problem in pools with stainless steel liners which maintain high water quality,as indicated earlfer.
M
~
64 O
i l
l 14.
D. H. Locke, " Review of Experience with Water Reactor Fuels 1968-l 1973," Nucl. Eng. and Desf on, Vol. 33, pp.94-124,1975.
15.
J. A. L. -Robertson, " Nuclear Fuel Failures, Their Causes and Remedies," Proceedinos of the Joint Tooical Meetino en Comercial Nuclear Fuel Tecnnolcov Tocav, CNS ISSN 0068-8517, April 28-10, 1975.
16.
P. E. Bobe, Fuel Performance of Licensed Nuclear Power Plants Through 1974, NUREG-0032, U.S. Nuclear Regulatory Comission, Wasnington, D.C., January 1976.
17.
F. Garzarolli, W. Diez, K.
P-. Franke and W. Fricke, " Corrosion and Hydriding of Zircaloy-2 and Jther Zirconium Alloys in SWR's,"
Proceedinos of British Nuclear Energy Ccnf., London, p.15, 52, July 1971.
18.
S. B. Dalgaard, "Long Term Corrosion and Hydriding of Zircaioy-4 Fuel. Clad in Comercial Pressurized Water Reactors with Forced Convective Heat Transfer," Presented at the Electrochemistry Society meeting, ',kshington, CC., May 2-7, 1976.
19.
K. J. Eger and A. Halsey, Oceratino Exoerience-Irraciated %~
Storage. G. E. Morris Oceration, NEDO-20969, Ge71eral Electr1c Co.,
San Jose, CA, June 1975.
20.
E.'E.* Voiland, Testimony presented at the California Energy and Resources Comission Hearings on Spent Fuel Storage, Sacramento,
~
California, March 10, 1977.
21.
Technical Descriotion in Suecort of Aeolication for FRSS Oceration, Occxet 70-1729, AG-2105, Alllac-General Nuclear Services, Rev1sec Decemoer 1974 22.
A. P. Larrick and O. Schneidunller, " Waste Management Imolications of Irradiated Nuclear Fuel Storage," UNI-SA-30, Novemcar 17, 1976, for presentation at IAEA Conference, Salzburg, Austria, May 2-13, 1977, IAEA-CN-36/23 (III.2).
23.
Sumary of Testimony Recarding Scent Fuel Assembly Storace, Cali-fornia Puolic Resources Coce 25524.1, Maren 10, 1977, Occxet
. Nos. 76-NL-1 and 76-NL-3, issued May 25, 1977.
24 Ref. 3, p. 3.34 25.
Safety Evaluacion Reecrt for Morris Ocention Fuel Storace Ex:ansicn, NEDO-20825, General Electr1c Co., San Jose, CA, Maren is75.
i 25.
P. Cohen, Water Coolant Technoloov of Pcwer Reactors, Gorton and Breach Science Puoi1cners, New Yorx,1969, p.159.
27.
K. L. Humpe-t and G. Zimerman, "Ex:erierce with Regard to Long-7a :
Storage of LWR Fuel Elements" (In German), AED-CCNF-77-013-il2, Reactor Congress, Mannheim, Mt th 29-Apri1 1,1977, pp.u7 450.
80 s.
28.
J. H. Austin, T. S. Elleman and K. Verghese, Tritium Diffusion in Zircaloy-2 in the Temperature Range -78 to 204*C, J. Nucl. Mat.,
Vol. 51, pp. 321-329, 1974.
29.
C. E. Ells, " Delayed Hydrogen Cracking in Zirconium Alloys," To.'
Appear in the Proceedings of the Third Symposium on Engineering Applications of Solid Mechanics.
30.
A. Garlik, " Stress Corrosion Cracking of Zirconium Alloys in Icdine Vapor," Proceedings of the British Nuclear Energy Society Meeting, July 1-2,.1971, London, Paper No. 3.
31.
J. C. Wood, " Environmentally Induced Fracture of Zircaloy by. Icdine and Cesium:
The Effects of Strain Rate, Localized Stresses and Temperature," J. Nucl. Mat., Vol. 57, pp.155-179,1975.
32.
- 8. Cox, " Environmentally Induced Cracking of Zirconium Alloys,"
Reviews on Caatings and Corrosion, Vol. I, No. 4, pp. 367-417, 1975.
33.
D. Cubbicciotti, J. E. Saneki, R. V. Strain, S. Greenberg, L 3
Neimark and C. E. Johnson, The Nature of Fission-Preduct De Inside Licht-Water-Reactor Fuel Reds, EPRI Project No. RP 4:.
Stanfore Researen Institute, Menlo Park, CA. Report prepared for Electr'.c Power Research Institute, Noveaber 1976.
34 M. G. Adamson and E. A. Aitken, Recent Advances in the Delineatien of the Mechanism of Fis'sion-Product-Incucec At:acx in ivoe-316 Stainless Steel Cladcing, GEAP-14136, General Electr1c Co., Sunnyvale, CA, August 1976.
35.
J. F. Remark,' A. 8. Johnson, Jr., H. Farrar, IV, and D. G. Atteridge,
" Helium Charging of Metals by Tritium Decay," Nucl. Tech. Vol 29, pp. 369-377, 1976.
36.
Not used.
37.
R. L. Gillon and H. P. Maffei, Metallurev Research/Chemicai Metallurev Studies in Succort of Irraolation Process 1nc Cecar en:
on tne Low-Temoerature Zircalov-2 Process Tuoe Hver1olne Preciem, BNWL-CC-329, Battelle, Pacific Nortawest Lacorator1es, R1cnianc, WA, October 14, 1965.
38.
S. Xass, " Aqueous Corrosion at the Zir:21oys at Low Temperatures",
J. Nucl. Mat., Vol. 23, pp. 315-321,1969.
39.
D. G. Sease and T. T. Vandergraaf, "The Canadian Spent Fuel Storage Canister:
Some Materials Aspects," Nucl. Tech., Vol. 32, po. 50-71,' January 1977.
40.
A. S. Johnson, Jr., D. R. Pratt and G. E. Ifma, A Survev of Materials and Cor osion Per ormance in Orv Cooline Acolica:1cns, aNWL-is55, e
Battaile Pac 1f1c Nortnwest Lacoratories, R1calanc, WA, Maren 1975.
l
41.
E. G. Brush and W. L. Pearl, " Corrosion and Corrosion Product Release in Neutral Feedwater," Corrosion, Vol. 28, p.129,1972.
i m
42.
O. De G. Jones and Dr. J. F. Newnan, " Aqueous Corrosion of Oxidized Stainless Steel Fuel Element Canning Material," Proceedines of the Fifth International Congress on Metallic Corrosion, Tokyo, Japan, May 1972, National Association of Corrosion Engineers, Houston, TX, pp. 908-912, 1974.
43.
Ref. 26, p. 221, 233, 288.
44 G. R. Bloom and T. F. Damitt, Corrosion and Baron Geoasition in Boric Acid Solutions, BNWL-520, Sattelle,7acific Nortnwest Lacora-tories, Ricnland, WA, Dicember 1967.
)
45.
O. G. Sammarone, The Galvanic Behavior of Materials in Reactor Coolants, WCAP-1844, Westinghouse Electric Corp., Pittsourgn, PA, August 1961.
46.
A. 8. Johnson, Jr., "A Review of Corrosion Phenomena on Zirconium Alloys, Niobium, Titanium, Inconel, Stainless Steel and Nickel Plate Under Irradiation," Reviews on Coatines and Corrosion, Vol.
I, No. 4, pp. 299-365,1975.
47.
L. Lunde "Special Features of External Corrosion of Fuel Cladding in Sailing Water Reactors," Nucl. Enc. and Desien, Vol. 33, po.
178-195, 1975.
x 48.
W. R. Smalley, Saxton Core II Fuel Per#crmance Evaluation: Part I Materials, WCAP-3385-56, Westingneuse Nuclear Energy Systems, Pittsourgn, PA, September 1971.
49.
Retrievable Surface Storace Facility Alternative conceots Encineerine Stueles, ARM-2SS8 REV, Atlant1c R1cnfiele Hanforc Co., R!cnianc, 'aA, July 1974 50.
R..L. Cowan, II, and C. S. Tedman, Jr., "Intergranular Cor-esion of Iron-Nickel-Chremium Alloys," Advances in Corrosion Science and Technolocy, Vol. '3, edited by M. G. Fontana anc R. W. Staenie, Plenun Press, New York, pp. 293 400, 1973.
51.
- 8. Cox, " Effects of Irradiation on the Oxidation of Zirconium Alloys in High Temcerature Aqueous Environments,".J.
Nucl. "a:.,
Vol. 23, pp. 1-47, 1963.
52.
Biolooical Research Annual Recor*-1962, HW-23636, General Electri Co., Ricniano, 'nA, Ju ly 7,1953, pp.99-109.
53.
Ecciocical Sciences Annual Recort-1974, SNWL-1950 Part II, Ba:talle Pac 1f1c.Nortnwes Lacoratories, Ricaland, WA, p. 25.
54 Ref. 6, p. 12.
82
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