Synthetic neutron camera and spectrometer in JET based on AFSI-ASCOT simulations

Paula Sirén, Jari Varje, Henri Weisen, Tuomas Koskela, JET Contributors

    Research output: Contribution to journalArticleScientificpeer-review

    8 Citations (Scopus)


    The ASCOT Fusion Source Integrator (AFSI) has been used to calculate neutron production rates and spectra corresponding to the JET 19-channel neutron camera (KN3) and the time-of-flight spectrometer (TOFOR) as ideal diagnostics, without detector-related effects. AFSI calculates fusion product distributions in 4D, based on Monte Carlo integration from arbitrary reactant distribution functions. The distribution functions were calculated by the ASCOT Monte Carlo particle orbit following code for thermal, NBI and ICRH particle reactions. Fusion cross-sections were defined based on the Bosch-Hale model and both DD and DT reactions have been included. Neutrons generated by AFSI-ASCOT simulations have already been applied as a neutron source of the Serpent neutron transport code in ITER studies. Additionally, AFSI has been selected to be a main tool as the fusion product generator in the complete analysis calculation chain: ASCOT - AFSI - SERPENT (neutron and gamma transport Monte Carlo code) - APROS (system and power plant modelling code), which encompasses the plasma as an energy source, heat deposition in plant structures as well as cooling and balance-of-plant in DEMO applications and other reactor relevant analyses. This conference paper presents the first results and validation of the AFSI DD fusion model for different auxiliary heating scenarios (NBI, ICRH) with very different fast particle distribution functions. Both calculated quantities (production rates and spectra) have been compared with experimental data from KN3 and synthetic spectrometer data from ControlRoom code. No unexplained differences have been observed. In future work, AFSI will be extended for synthetic gamma diagnostics and additionally, AFSI will be used as part of the neutron transport calculation chain to model real diagnostics instead of ideal synthetic diagnostics for quantitative benchmarking.
    Original languageEnglish
    Article numberC09010
    JournalJournal of Instrumentation
    Issue number9
    Publication statusPublished - 8 Sept 2017
    MoE publication typeA1 Journal article-refereed


    This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement number 633053 and from Tekes — the Finnish Funding Agency for Innovation under the FinnFusion Consortium. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The calculations presented above were performed in part using computer resources within the Aalto University School of Science “Science-IT” project.


    • analysis and statistical methods
    • nuclear instruments and methods for hot plasma diagnostics
    • simulation methods and programs
    • Simulation methods and programs
    • Analysis and statistical methods
    • Nuclear instruments and methods for hot plasma diagnostics


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