Skip to main content
Log in

The control of tritium in ETHEL

  • Published:
Journal of Fusion Energy Aims and scope Submit manuscript

Abstract

The operation of the European Tritium Handling Experimental Laboratory (ETHEL) will require the implementation of means and procedures for allowing tritium control within the facility. For that purpose, account must be taken of the particular characteristics of tritium, such as its high mobility, capacity to dissolve in materials, often limited precision when performing inventory measurements. This paper estimates the influence of these effects on the overall tritium balance in ETHEL. By employing available models for predicting tritium hold-up, it is estimated that three to four grams of tritium may potentially remain irreversibly fixed in various plant items of the standard laboratory infrastructure (exclusive of experimental circuits). On the other hand, the highest overall precision that may be attained with the present plant regarding inventory measurements is estimated to be of the order of few percent. On the basis of the above estimates, the allowable limits for the Material Unaccounted For (MUF) are discussed.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. Agreement in the form of an exchange of letters between the European Atomic Energy Community (Euratom) and the Government of Canada amending the Agreement between the European Atomic Energy Community (Euratom) and the Government of Canada for cooperation in the peaceful uses of atomic energy of October 6, 1959, Official Journal of the European Communities No. 91/C 215/05.

  2. R. Kraemeret al. Common Tritium Control Methodology Proposed for Two Civil Tritium Facilities ETHEL & TLK, Proceedings of the 15th ESARDA Symposium on Safeguards and Nuclear Material Management, Rome, May 11–13, 1993.

  3. G. Vassallo et al. (1992). Design, construction, commissioning, licensing and future operational aspects of the European tritium handling experimental laboratory.Fusion Technol. 21, 235–240.

    Google Scholar 

  4. C. Housiadas, F. Tinagli, and G. Vassallo. Estimate of routine tritium discharges from ETHEL.J Fusion Energy (to appear).

  5. Cecchi, J. L. (1979). Tritium permeation and wall loading in TFTR vacuum vessel.J. Vac. Sci. Technol. 16, 58–70.

    Google Scholar 

  6. M. P. Riehm, W. W. Smeltzer, and D. A. Thompson. Hydrogen—Solid Interaction and Tritium Permeation Barriers, Report CFFTP-G-86041, 1986.

  7. R. E. Ellefson, C. N. Lindsay, and E. E. Johns (1988). Measurement and prediction of tritium holdup.Fusion Technol. 14, 1036–1040.

    Google Scholar 

  8. J. T. Gill, R. E. Ellefson, and W. M. Rutherford. Tritium Inventory Differences II: Molecular Sieve Holdup, Proceedings of the Institute of Nuclear Materials Management 27th Annual Meeting, New Orleans, June 22–25, 1986, pp. 94–104.

  9. ENEA (1987). Guida Tecnica No 26, Gestione dei Rifiuti Radioattivi.Sicurezza e Protezione 14.

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Housiadas, C., Perujo, A. & Vassallo, G. The control of tritium in ETHEL. J Fusion Energ 13, 21–26 (1994). https://doi.org/10.1007/BF02214044

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF02214044

Key Words

Navigation