Hostname: page-component-77c89778f8-rkxrd Total loading time: 0 Render date: 2024-07-17T03:30:41.655Z Has data issue: false hasContentIssue false
  • English
  • Français

Characterization of Mechanical Strengths for Simulated High-Level Waste Forms

Published online by Cambridge University Press:  21 February 2011

Hiroshi Igarashi  and
Takeshi Takahashi
Hiroshi Igarashi
Affiliation:
Power Reactor & Nuclear Fuel Development Corp.(PNC) 4–33,Muramatsu, Tokai-mura, Ibarakl, 319–11, JAPAN
Takeshi Takahashi
Affiliation:
Power Reactor & Nuclear Fuel Development Corp.(PNC) 4–33,Muramatsu, Tokai-mura, Ibarakl, 319–11, JAPAN
Get access

Abstract

Waste forms have been developed and characterized at PNC (Power Reactor and Nuclear Fuel Development Corporation)to immobilize high-level liquid waste generated from the reprocessing of nuclear spent fuel.

Mechanical strength tests were excecuted on simulated solidified highlevel waste forms which were borosilicate glass and diopside glass-ceramic. Commercial glass was tested for comparison. Measured strengths were three-point bending strength,uniaxial compressive strength,impact strength by falling weight method,and Vickers hardness. Fracture toughness and fracture surface energy were also measured by both notch-beam and indentation technique.

The results show that mechanical strengths of waste glass form are similar and that the glass ceramic form has the higher fracture toughness.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 433
Copyright
Copyright © Materials Research Society 1990

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

[1] Mendel, J.E., et al, PNL-3802, April, 1982.Google Scholar
[2] Glass Handbook, edited by Sakka, S., et al.(Asakura Shoten, Tokyo, 1975), pp 683–687.Google Scholar
[3] Richter, H., et al., Scientific Basis for Nuclear Waste Management V edited by Lutze, W. (Elsvier Science Publishing Co., New York, 1982),p. 229.Google Scholar
(4] Evance, A.G. and Charles, E.A., J.Am.Cer.Soc. 59 (7-8), 371 (1976).Google Scholar
[5] Weber, W.J., et al., J.Mat.Sci. 19, 2533–2544 (1984).Google Scholar
[6] Wallace, R.M. and Kelley, J.A., DP-1400 (1976).Google Scholar
[7] Anstis, A., Chantikul, P., Lawn, B.R., et al., J.Am.Cer.Soc., 64 (9), 533 (1981).Google Scholar
[8] Igarashi, H., et al., Proceedings of 1982 Annual Meeting of the Atomic Energy Society of Japan, II, p.322 (1982).Google Scholar
[9] Bansal, G.K. et al., ASTM STP678, p.38.Google Scholar
[10] Chermant, J.L., Verres et Refractaires, 33 (6), 843 (1979).Google Scholar
[11] Vernaz, E., et al., The Second International Symposium on Ceramics in Nuclear waste Management, 1983, edited by Wicks, G.G., et al.(Am.Cer.Soc., 1984), pp.687–696.Google Scholar
[12] Lutze, W., Radioactive Waste Forms for The Future, edited by Lutze, W. and Ewing, R.C. (North-Holland, 1988), pp.51–66.Google Scholar