Abstract
After discharge from the reactor core, the fuel elements are stored on the reactor site for a period of at least one year to allow for radioactivity decay and cooling. The reactor plant proper usually has a fuel storage capacity of at least three years’ discharge volume in addition to a full standby core inventory. The use of compact storage racks with neutron absorbers allows this storage capacity even to be extended to nine years’ discharge volume. Spent fuel elements are then transported in spent fuel casks either to intermediate storage facilities or to storage pools at reprocessing plants. Table 7–1 shows the fuel characteristics of discharged fuel elements for different converter reactors and LMFBR’s. The total activity, expressed in Ci/kg, for various times after discharge is very similar for fuel of converter and breeder reactors.
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Selected Literature
Transport and storage of spent fuel elements
Brennelement-Zwischenlager Ahaus. Hannover: Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen (DWK). 1979.
International Nuclear Fuel Cycle Evaluation, Spent Fuel Management. Report of INFCE Working Group 6. Vienna: International Atomic Energy Agency. 1980.
The Safe Transport of Radioactive Materials. Special Issue. IAEA Bulletin 21 (6), 2–75 (1979).
Shipments of Nuclear Fuel and Waste: Are They Really Safe? Washington: US Department of Energy, DOE/EV-0004 (1977).
Spent Fuel Storage Factbook: Facts Booklet. Washington: US Department of Energy, DOE/NE-005 (1980).
Transportbehälter - Die trockene Lagerung von ausgedienten Brennelementen. Hannover: Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen (DWK). 1979.
Uranium/plutonium fuel cycle
Baumgärtner, F.: Chemie der nuklearen Entsorgung. München: Karl Thiemig. 1978.
Benedict, M., et al.: Nuclear Chemical Engineering. New York: McGraw-Hill. 1981.
Bericht über das in der Bundesrepublik Deutschland geplante Entsorgungszentrum für ausgediente Brennelemente aus Kernkraftwerken. Hannover: Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen (DWK). 1977.
Cohen, B.: High-level Radioactive Waste from Light Water Reactors. Reviews of Modern Physics 49, 1–20 (1977).
Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors (GESMO). Washington: US Nuclear Regulatory Commission, NUREG-002 (1976).
Fischer, U., Wiese, H.W.: KORIGEN - Ein Programm zur Bestimmung des nuklearen Inventars von Reaktorbrennstoffen im Brennstoffkreislauf Kernforschungszentrum Karlsruhe, KfK-3014 (1982).
Haug, H.O.: Zerfallsrechnungen verschiedener mittelaktiver und actinidenhaltiger Abfälle des LWR-Brennstoffkreislaufs; Teil I: Modellmäßig abgeleitete Basisdaten, Aktivität und Wärmeleistung; Teil II: Radiotoxizitätsvergleich. Kernforschungszentrum Karlsruhe, KfK-3221 (Part I) and KfK-3222 (Part II) (1981).
Kennies, H.H., Körting, K.: Nukleare Sicherheit von Wiederaufarbeitungsanlagen. Kernforschungszentrum Karlsruhe, KfK-2399 (1976).
International Nuclear Fuel Cycle Evaluation, Reprocessing, Plutonium Handling, Recycle. Report of INFCE Working Group 4. Vienna: International Atomic Energy Agency. 1980.
Lakey, L.T.: A Safety Analysis for the Nuclear Fuel Recovery and Recychng Center. Nuclear Technology 43, 213–221 (1979).
Leblanc, J.M., Vanden Bemden, E.: Chemical Aspects of Mixed Oxide Fuel Production. Radiochimica Acta 25, 149–152 (1978).
Rapin, M.: Reprocessing: Experience and Outlook. In: World Nuclear Energy - Accomphshments and Perspectives, Proc. Int. Conference Washington, 17–21 November 1981. Transactions American Nuclear Society 37, 176–183 (1981).
Thorium/U-233 fuel cycle
Feraday, M.A.: Remote Fabrication of (U-233/Th) O2 Pellet-Type Fuels for CANDU Reactors. Transactions American Nuclear Society 32, 233–234 (1979).
International Nuclear Fuel Cycle Evaluation, Advanced Fuel Cycle and Reactor Concepts. Report of INFCE Working Group 8. Vienna: International Atomic Energy Agency. 1980.
Lotts, A.L., et al.: HTGR Fuel and Fuel Cycle Technology. In: Nuclear Power and Its Fuel Cycle, Proc. Int. Conference, Salzburg, 2–13 May 1977, Vol. 3, pp. 433–452. Vienna: International Atomic Energy Agency. 1977.
Merz, E.: Wiederaufarbeitung thoriumhaltiger Kernbrennstoffe im Lichte proliferationssicherer Brennstoffkreisläufe. Naturwissenschaften 65, 424–431 (1978).
Orth, D.A.: Savannah River Plant Thorium Reprocessing Experience. Nuclear Technology 43, 63–74 (1979).
Report to the American Physical Society by the Study Group on Nuclear Fuel Cycles and Waste Management (Pines, D., ed.). Reviews of Modern Physics 50 (1), Part II (1978).
Zimmer, E., et al.: Aqueous Chemical Processes for the Preparation of High Temperature Reactor Fuel Kernels. Radiochimica Acta 25, 161–169 (1978).
Uranium/plutonium fuel cycle of fast breeder reactors
Allardice, R.H. et al.: Fast Reactor Fuel Reprocessing in the United Kingdom. In: Nuclear Power and Its Fuel Cycle, Proc. Int. Conference, Salzburg, 2–13 May 1977, Vol. 3, pp. 615–630. Vienna: International Atomic Energy Agency. 1977.
Auchapt, P., et al.:The French R&D Programme for Fast Reactor Fuel Reprocessing. In: Fast Reactor Fuel Reprocessing, Proc. Symposium, Dounreay, 15–18 May 1979, pp. 51–59. London: Society of Chemical Industry. 1980.
Barret, T.R.: The Reconstruction of the Fast Reactor Reprocessing Plant, Dounreay. In: Fast Reactor Fuel Reprocessing, Proc. Symposium, Dounreay, 15–18 May 1979, pp. 17–35. London: Society of Chemical Industry. 1980.
Baumgärtner, F., Ochsenfeld, W.: Development and Status of LMFBR Fuel Reprocessing in the Federal Republic of Germany. Kernforschungszentrum Karlsruhe, KfK-2301 (1976).
Bishop, J.F., etal.: Fast Reactor Fuel Design and Development. In: Nuclear Power and Its Fuel Cycle, Proc. Int. Conference, Salzburg, 2–13 May 1977, Vol. 3, pp. 377–391. Vienna: International Atomic Energy Agency. 1977.
Ebert, K.H.: Die Wiederaufarbeitung von Schnellbrüter-Brennelementen. Atomkernenergie/Kerntechnik 36, 259–263 (1980).
Funke, P., et al.: Weiterentwicklung des oxidischen Brennstoffes zum Schnellbriitereinsatz. Atomkernenergie/Kerntechnik 36, 253–258 (1980).
International Nuclear Fuel Cycle Evaluation, Fast Breeder Reactors. Report of INFCE Working Group 5. Vienna: International Atomic Energy Agency. 1980.
Sauteron, J.: Technologie du retraitement des combustibles des réacteurs rapides. In: Nuclear Power and Its Fuel Cycle, Proc. Int. Conference, Salzburg, 2–13 May 1977, Vol. 3, pp. 633–645. Vienna: International Atomic Energy Agency. 1977.
Waste conditioning and waste disposal
Closs, K.D.: Vergleich der verschiedenen Entsorgungsalternativen und Beurteilung ihrer Reahsierung. Kernforschungszentrum Karlsruhe, KfK-3000 (1980).
Environmental Aspects of Commercial Radioactive Waste Management. Washington: US Department of Energy, DOE/ET-0029 (1979).
Environmental Survey of the Reprocessing and Waste Management Portions of the LWR Fuel Cycle. Washington: US Nuclear Regulatory Commission, NUREG-0016 (1976).
International Nuclear Fuel Cycle Evaluation, Waste Management and Disposal. Report of INFCE Working Group 7. Vienna: International Atomic Energy Agency. 1980.
Rothemeyer, H., Closs, K.D.: High Level Waste Disposal. In: World Nuclear Energy - Accomplishments and Perspectives, Proc. Int. Conference, Washington, 17–21 November 1981. Transactions American Nuclear Society 37, 165–174 (1981).
Technology of Commercial Radioactive Waste Management. Washington: US Department of Energy, DOE/ET-0028 (1979).
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© 1983 Springer-Verlag Wien
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Kessler, G. (1983). Technical Aspects of Nuclear Fuel Cycles. In: Nuclear Fission Reactors. Topics in Energy. Springer, Vienna. https://doi.org/10.1007/978-3-7091-7622-1_7
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