Hostname: page-component-78c5997874-s2hrs Total loading time: 0 Render date: 2024-10-31T23:01:30.618Z Has data issue: false hasContentIssue false
  • English
  • Français

Cooling and Cracking of Technical HLW Glass Products: Experimental and Numerical Studies

Published online by Cambridge University Press:  26 February 2011

Bernhard Kienzler
Bernhard Kienzler*
Affiliation:
Kernforschungszentrum Karlsruhe GmbH, Institut für Nukleare Entsorgungstechnik, Postfach 3640, D-7500 Karlsruhe 1, Federal Republic of, Germany
Get access

Abstract

Various cooling procedures have been applied to canisters filled with inactive simulated HLW glass and the measured temperature distributions have been compared with numerically computed data. Stress computations of the cooling process were carried out with a finite element method. Only those volume elements having temperatures below the transformation temperature Tg were assumed to contribute thermoelastically to the developing stresses. Model calculations were extended to include real HLW glass canisters with inherent thermal power. The development of stress as a function of variations of heat flow conditions and of the radioactive decay was studied.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 191
Copyright
Copyright © Materials Research Society 1989

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. Kerkhof, F., in Glastechnische Fabrikationsfehler, edited by Jebsen-Marwedel, H., Bruckner, R. (Springer Verlag, Berlin, Heidelberg, New York, 1980), p. 50 Google Scholar
2. Weymann, H.D., J. Am. Ceramic Soc. 45 (11), 517–522 (1962)CrossRefGoogle Scholar
3. Blank, K., Glastechn. Ber. 52 (1), 1–13 (1979)Google Scholar
4. Institut für Nukleare Entsorgungstechnik, KfK 4228, 1987 Google Scholar
5. Peters, R.D., Slate, S.C., Nucl. Eng. Design 67, 425–445 (1981)CrossRefGoogle Scholar
6. Farnsworth, R.K., PNL-SA-13812, 1986 Google Scholar
7. ADINA Engineering Inc., ADINAT - A Finite Element Program for Automatic Dynamic Incremental Nonlinear Analysis of Temperatures, ADINA Engineering Inc. Watertown, Massachusetts, Report AE 81–2, 1981 Google Scholar
8. ADINA Engineering Inc., ADINA - A Finite Element Program for Automatic Dynamic Incremental. Nonlinear Analysis, ADINA Engineering Inc. Watertown, Massachusetts, Report AE 81–1, 1981, Revised 1984.Google Scholar
9. Martin, D.M., NUREG/CR-4198, 1985 Google Scholar
10. Sato, S., Furuya, H., Nishino, Y., Sugisaki, M., Nuclear Technology, 70, 235–242 (1985).CrossRefGoogle Scholar
11. Ashly, M.F., Jones, D.R.H., Engineering Materials II (Pergamon Press, Oxford 1986).Google Scholar
12. Matzke, Hj., Toscano, E., Routbort, J., Reimann, K., J. Am. Cerare. Soc. 69, C–138-C-139 (1986)Google Scholar