Abstract
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 language | English |
|---|---|
| Article number | C09010 |
| Journal | Journal of Instrumentation |
| Volume | 12 |
| Issue number | 9 |
| DOIs | |
| Publication status | Published - 8 Sept 2017 |
| MoE publication type | A1 Journal article-refereed |
Funding
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.
Keywords
- 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
