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Treatment and geological disposal of waste from NET pre-design

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Abstract

Within the European Fusion Technology programs Studsvik RadWaste AB has performed studies on fusion waste treatment and disposal for several years. This paper deals with the treatment and geological disposal of radioactive waste from NET operation and decommissioning. Results from calculations on radioactive waste fluxes for the operation and decommissioning of NET are reported. The calculations are based on the NET predesign report published 1993 and include results for the exchangeable in-vessel and external parts of the machine as well as permanent reactor components. Different aspects of treatment, packaging, transportation, and interim storage of the waste are discussed. The volumes of waste conditioned for final disposal are preliminarily quantified, according to German and Swedish scenarios for radioactive waste disposal. A total repository volume of approximately 45,000 m3 is required in the German Scenario and 35,000 m3 is required in the Swedish Scenario. Results from dose rate calculations for NET waste in final repositories are presented for the Swedish Scenario. This work was financially supported by the Swedish Natural Science Research Council (NFR) and the European Atomic Energy Community, under an association contract between Euratom and Sweden.

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References

  1. NET team (1993). NET predesign report.Fusion Engineering and Design 21, 1–358.

    Google Scholar 

  2. P. Brennecke and E. Warnecke (1987). Anforderungen an Endzusulagernde Radioaktive Abfälle, Vorläufige Endlagerungsbedingungen, Stand, November 1986—Schachtanlage Konrad. PTB, Bericht SE-16.

  3. P. W. Brennecke and E. H. Warnecke (1991). Preliminary waste acceptance requirements—Konrad Repository Project.Nucl. Energy 30, 173–181.

    Google Scholar 

  4. E. Warnecke and K. Ermisch (1989). The Planned Gorleben Repository—Present Status, New Data Provided by the Utilities on Wastes Produced, and Future Directions. Safety of the Nuclear Fuel Cycle, Weinheim, pp. 297–319.

  5. K.-D. Closs (1987). Überblick über die weiterführenden Arbeiten zur direkten Endlagerung.Kerntechnik 50, 45.

    Google Scholar 

  6. SKB (1987). Slutförvar för reaktoravfall—SFR. Slutlig säkerhetsrapport SFR 1. Swedish Nuclear Fuel and Waste Management Co., SKB.

  7. SKB (1992). Plan 92, Kostnader för kärnkraftens radioaktiva restprodukter. Swedish Nuclear Fuel and Waste Management Co., SKB.

  8. K. Brodén and G. Olsson. Management and Final Disposal of Radioactive Waste from NET (to be published as a Studsvik Report).

  9. ITER Design Information Document. ITER-90-1.

  10. W. Gulden, Private communication, December 1992.

  11. I. Aggeryd, L. Devell, and G. Olsson (1992). NET/ITER Radioactive Waste Fluxes for the Operational Phases and Decommissioning. Studsvik Technical Note NW-92/32.

  12. P. Rocco and M. Zucchetti (1992). Activation Calculations for ITER with the NET Shielding Blanket. ISPRA Technical Note, Draft.

  13. M. Zucchetti (1992). Activation Calculation for ITER with the NET Driver Blanket. JRC-ISPRA Technical Note, Draft.

  14. M. Lindberg and I. Aggeryd (1993). Radioactive Waste Fluxes from NET Operation and Decommissioning. Studsvik Report RW-93/21.

  15. R. Pulkkinen, B. Hagel, J. Berntsson, and S. Pettersson (1988). Waste Production Costs for Waste Handling Including Transport and Final Storage for Swedish Reactor Plants. Proc of the International Symposium on Management of Low- and Intermediate-Level Radioactive Waste, Stockholm, May 16–20, IAEA-SM-303/44.

  16. I. Aggeryd, L. Devell, and G. Olsson. Waste Management and Final Disposal of NET/ITER Radioactive Waste. Studsvik Technical Note NW-92/33.

  17. W. Guldenet al. (1989). Fusion Waste Management. Safety and Environment Studies 1985–86. NET Report No 92, EUR-FU/XII-80/89-92.

  18. S. Hedlund (1992). Sammanställning av metoder för kapning av skrot. Studsvik Technical Note NS-89/102.

  19. IAEA (1985). Regulations for Safe Transport of Radioactive Material. IAEA Safety Series No. 6.

  20. I. Aggeryd and U. Bergström (1990). Doses to Man due to Leakage into the Biosphere of Fusion Waste Nuclides Disposed of in a Repository. Studsvik Technical Note NS-90/10.

  21. U. Bergströmet al. (1982). BIOPATH—A Computer Code for Calculation of the Turnover of Nuclides in the Biosphere and the Resulting Doses to Man. Studsvik Report NW-82/261.

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Authors and Affiliations

  1. Studsvik RadWaste AB, S-611 82, Nyköping, Sweden

    Karin Brodén, Ingrid Aggeryd, Maria Lindberg & Gunnar Olsson

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  1. Karin Brodén
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  2. Ingrid Aggeryd
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  3. Maria Lindberg
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  4. Gunnar Olsson
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Brodén, K., Aggeryd, I., Lindberg, M. et al. Treatment and geological disposal of waste from NET pre-design. J Fusion Energ 12, 209–214 (1993). https://doi.org/10.1007/BF01059380

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