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Part of the book series: NATO ASI Series ((ASDT,volume 2))

Abstract

Excellent neutron economy and on-line refuelling allow CANDU reactors to operate on a variety of fuel cycles. Atomic Energy of Canada Limited (AECL) has an on-going program exploring fuel options [1,2]. The motivation includes fissile resource extension, fuel cycle economics, and waste management, environmental, political and strategic considerations. Technically, several fuel cycles are ready for exploitation, but at present all Canadian reactors use the natural uranium (NU) fuel cycle.

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References

  1. Torgerson, D.F., Boczar, P.G., Dastur, A.R. (1994), CANDU Fuel Cycle Flexibility, 9th Pacific Basin Nuclear Conference, Sydney, Australia.

    Google Scholar 

  2. Veeder, J., Didsbury, R. (1985), A Catalogue of Advanced Fuel Cycles in CANDU PHW Reactors, AECL-8641.

    Google Scholar 

  3. Milgram, M.S. (1986), Thorium Fuel Cycles in CANDU Reactors: A Review, AECL-8326.

    Google Scholar 

  4. Lane, A.D. et al. (1993), CANFLEX: A Fuel Bundle to Facilitate the Use of Enrichment and Fuel Cycles in CANDU Reactors, Proc. IAEA Technical Committee Meeting on Advances in Heavy Water Reactors, Toronto, Canada.

    Google Scholar 

  5. Boczar, P.G. et al. (1992), A Low Void Reactivity CANDU Fuel Bundle, Proc. 3rd Int. Conf. on CANDU Fuel, Chalk River, Canada.

    Google Scholar 

  6. Hardman, J., Dastur, A.R. (1992), CANDU Nuclear Power Plant Optimization with MOX Fuel Cycles, Int. Conf. in Design and Safety of Advanced Nuclear Power Plants, Tokyo.

    Google Scholar 

  7. Boczar, P.G., Hastings, I.J., Celli, A. (1989), Recycling in CANDU of Uranium and/or Plutonium From Spent LWR Fuel, IAEA Tech. Cttee. Mtg. on Recycling of Pu and U in Water Reactor Fuels, Cadarache, AECL-10018.

    Google Scholar 

  8. Keil, H., Boczar, P.G., Park, H.S. (1992), Options for Direct Use of Spent PWR Fuel in CANDU (DUPIC), Proc. 3rd Int. Conf. on CANDU Fuel, Chalk River, Canada.

    Google Scholar 

  9. Gratham, L.F. et al. (1980), AIROX Dry Pyrochemical Processing of Oxide Fuel; A Proliferation Resistant Method, Am. Chem. Soc. Symp. 117, 219.

    Google Scholar 

  10. Yang, M.S. et al. (1993), Conceptual Study of DUPIC Fuel Manufacturing Technology, Proc. Int. Conf. on Future Nuclear Systems, Emerging Fuel Cycles and Waste Disposal Options (GLOBAL 93), Seattle.

    Google Scholar 

  11. Pillay, K.K.S. (1993), Safeguards and Non-Proliferation Aspects of Dry Fuel Recycling Technology, GLOBAL 93, op. cit.

    Google Scholar 

  12. Dastur, A.R. et al. (1994), Annihilation of Plutonium in CANDU Reactors, IAEA Tech. Cttee Mtg. on Unconventional Options for Pu-Dispositioning, Obninsk.

    Google Scholar 

  13. Carter, T.J. (1986), The Recycle Fuel Fabrication Laboratory at Chalk River, Proc. First Int. Conf. on CANDU Fuel, Can. Nucl. Soc.

    Google Scholar 

  14. Jones, R.T., Griffiths, J., Okazaki, A. (1989), Reactor Physics Measurements in Support of Advanced Fuel Cycles in CANDU Reactors, AECL-10004.

    Google Scholar 

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© 1995 Springer Science+Business Media Dordrecht

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Boczar, P.G., Kupca, S., Fehrenbach, P.J., Dastur, A.R. (1995). Plutonium Burning in CANDU. In: Merz, E.R., Walter, C.E., Pshakin, G.M. (eds) Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors. NATO ASI Series, vol 2. Springer, Dordrecht. https://doi.org/10.1007/978-94-017-2288-9_8

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  • DOI: https://doi.org/10.1007/978-94-017-2288-9_8

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-90-481-4549-2

  • Online ISBN: 978-94-017-2288-9

  • eBook Packages: Springer Book Archive

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