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Assessment of Crevice Corrosion and Hydrogen Induced Stress Corrosion Cracks of Ti-Pd Alloys for HLW Overpack In Deep Underground Water Environments

Published online by Cambridge University Press:  11 February 2011

Guen Nakayama
Affiliation:
Research Laboratory, Ishikawajima-Harima Heavy Industries, Co., Ltd.
Koichi Murakami
Affiliation:
Research Laboratory, Ishikawajima-Harima Heavy Industries, Co., Ltd.
Masatsune Akashi
Affiliation:
Research Laboratory, Ishikawajima-Harima Heavy Industries, Co., Ltd.
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Abstract

Crevice corrosion and hydrogen-induced stress corrosion cracking tendencies of titanium (Ti) alloys in deep underground water environments are investigated in the present paper. The crevice corrosion repassavation potential, ER,CREV of Ti-palladium (Pd) alloys was measured and compared with the free corrosion potential, ESP = +0.32 V vs. SHE. The minimum Pd content of the alloys for suppressing crevice corrosion in the envisaged most corrosive high-level radioactive waste (HLW) disposal environment, corresponding to the seawater originated underground water of 0.6 mol/L [NaCl] at 100 °C, is 0.05 %, Ti-Gr.17 alloy. The Pd content of 0.01 % is found to be sufficient for realizing satisfactory crevice corrosion resistance in transuranium (TRU) disposal environment of 0.6 mol/L [NaCl] at 80 °C. The hydrogen-induced stress corrosion cracking tendencies of the Ti alloys caused by the formation and cracking of hydride layers on alloy surfaces were assessed by galvanostatic and constant-load tests conducted in completely reducing environments. Test results indicate that Ti-Pd alloys are immune to stress-corrosion cracking in HLW underground disposal condition for 1000 years. Total electrical charge density in TRU waste overpacks for 60,000 years, estimated from analyses of thermal history in waste emplacement drifts, was found to be 7.5 MC/m2, suggesting the hydride layers formed were 30 μm thick and the crack depth was 15 μm on Ti-Gr.17. Thus, the depth of the stress-corrosion cracks is too small to be taken into engineering consideration. The above results suggest that Ti-Pd alloys with Pd content over 0.05 % for HLW and 0.01 % for TRU waste can be utilized as corrosion-resistant layers of waste-disposal containers of HLW and TRU waste.

Type
Research Article
Copyright
Copyright © Materials Research Society 2003

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References

REFERENCES

1. Nakayama, G., Naskamura, N., Fukuya, Y., Akashi, M., and Ueda, H., “Prediction of Long-Term Corrosion Behavior in Nuclear Waste Systems”, presented in Cadarache 26th to 29th, 2001 (unpublished).Google Scholar
2. Japan Nuclear Fuel Cycle Development Center, Japan Power Industries Association, “Conceptual Design of TRU Waste Disposal System”, JNC TY1400, 2000–001/TRU TR-2000–01 (2000).Google Scholar
3. Kawakami, S., Yamazaki, M., Kanno, A., and Asano, E.: IHI Technical Review 40, 185 (2000) (in Japanese).Google Scholar
4. Phillips, I.I., Poole, P. and Shreir, L.L., Corrosion Science 14, 533 (1974).Google Scholar
5. Nakamura, N., Akashi, M., Fukaya, Y., Nakayama, G., Ueda, H.: Zairyo to Kankyou 2000, 68 (2000) (in Japanese).Google Scholar
6. Environment Development Center for Nuclear Power Report, 2001 Survey Report on Development of Radioactive Waste Processing Systems-Development of Disposal Containers, (2002).Google Scholar