Nuclear performance analyses for HCPB test blanket modules in ITER

U. Fischer, P. Pereslavtsev, P. Kotiluoto, F. Wasastjerna

    Research output: Contribution to journalArticleScientificpeer-review

    5 Citations (Scopus)

    Abstract

    Neutronic, shielding and activation analyses have been performed for recent design variants of the Helium Cooled Pebble Bed (HCPB) test blanket module (TBM) in ITER on the basis of 3D Monte Carlo calculations. The main objective has been to assess and optimise the nuclear performance of the HCPB test blanket modules in terms of the tritium generation, the nuclear heating and the radiation shielding and provide, among others, the data required for the engineering design of the test modules. The shielding efficiency of the TBM system was shown to be sufficient to allow access of work personnel to the port extension after a waiting time of 10 days after shut down as required by ITER. The activation analyses provided the afterheat and activation data for quality assured safety analyses assuming a representative irradiation scenario.

    Original languageEnglish
    Pages (from-to)2140-2146
    JournalFusion Engineering and Design
    Volume82
    Issue number15-24
    DOIs
    Publication statusPublished - 1 Oct 2007
    MoE publication typeA1 Journal article-refereed

    Keywords

    • ITER
    • test blanket module
    • neutronics
    • Monte Carlo
    • fusion energy
    • fusion reactors

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