An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles

Pauli Juutilainen, Tuomas Viitanen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    Advanced nuclear fuel cycle scenarios were simulated with the COSI6 code, developed by CEA (France), to assess, how much the capacity of the planned nuclear waste repository at Olkiluoto (Finland) could be increased with the help of partitioning and transmutation (P&T) technologies. The repository capacity evaluation of this study is based on the comparison of the decay heats produced by the deposited waste in various scenarios. The COSI6 code is used for simulations to provide the repository decay heat curves. Applying the closed fuel cycle would change the disposal concept and schedule, because of which it is not quite straightforward to assess the impact of P&T on the capacity. However, it can be concluded that recycling the transuranic nuclides probably decreases the required volume for the disposal, but thermal dimensioning analysis is needed for more specific conclusions
    Original languageEnglish
    Title of host publicationProceedings of Global 2013
    Subtitle of host publicationNuclear Energy at Crossroads
    PublisherAmerican Nuclear Society ANS
    Pages1267-1275
    ISBN (Print)978-0-89448-704-0
    Publication statusPublished - 2013
    MoE publication typeNot Eligible
    EventGlobal 2013. International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads - Salt Lake City, Utah, United States
    Duration: 29 Sep 20133 Oct 2013

    Conference

    ConferenceGlobal 2013. International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads
    Abbreviated titleGlobal 2013
    CountryUnited States
    CitySalt Lake City, Utah
    Period29/09/133/10/13

    Fingerprint

    Nuclear fuels
    Radioactive wastes
    Thermoanalysis
    Isotopes
    Recycling
    Hot Temperature

    Keywords

    • COSI6
    • nuclear energy
    • closed fuel cycles
    • fast reactors
    • partitioning and transmutation

    Cite this

    Juutilainen, P., & Viitanen, T. (2013). An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles. In Proceedings of Global 2013 : Nuclear Energy at Crossroads (pp. 1267-1275). American Nuclear Society ANS.
    Juutilainen, Pauli ; Viitanen, Tuomas. / An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles. Proceedings of Global 2013 : Nuclear Energy at Crossroads. American Nuclear Society ANS, 2013. pp. 1267-1275
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    Juutilainen, P & Viitanen, T 2013, An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles. in Proceedings of Global 2013 : Nuclear Energy at Crossroads. American Nuclear Society ANS, pp. 1267-1275, Global 2013. International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads, Salt Lake City, Utah, United States, 29/09/13.

    An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles. / Juutilainen, Pauli; Viitanen, Tuomas.

    Proceedings of Global 2013 : Nuclear Energy at Crossroads. American Nuclear Society ANS, 2013. p. 1267-1275.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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    AB - Advanced nuclear fuel cycle scenarios were simulated with the COSI6 code, developed by CEA (France), to assess, how much the capacity of the planned nuclear waste repository at Olkiluoto (Finland) could be increased with the help of partitioning and transmutation (P&T) technologies. The repository capacity evaluation of this study is based on the comparison of the decay heats produced by the deposited waste in various scenarios. The COSI6 code is used for simulations to provide the repository decay heat curves. Applying the closed fuel cycle would change the disposal concept and schedule, because of which it is not quite straightforward to assess the impact of P&T on the capacity. However, it can be concluded that recycling the transuranic nuclides probably decreases the required volume for the disposal, but thermal dimensioning analysis is needed for more specific conclusions

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    Juutilainen P, Viitanen T. An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles. In Proceedings of Global 2013 : Nuclear Energy at Crossroads. American Nuclear Society ANS. 2013. p. 1267-1275