Neutronic simulations of in-vessel neutron calibrations for ITER neutron diagnostics by using simplified ITER model

•Neutron calibration experiments using a compact D-T neutron generator for ITER in-vessel neutron diagnostics have been simulated using MCNP with the simplified ITER model.•Angular neutron spectra from the compact D-T neutron generator have been evaluated for the source term of the MCNP calculation...

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Bibliographic Details
Published in:	Fusion engineering and design Vol. 191; p. 113548
Main Authors:	Nishitani, Takeo, Ishikawa, Masao, Cheon, Mun-Seong, Hong, Seong-Hee, Rodionov, Roman, di Sarra, Silvia, Krasilnikov, Vitaly, Gin, Dmitry, Coriton, Bruno
Format:	Journal Article
Language:	English
Published:	Elsevier B.V 01-06-2023
Subjects:	In-vessel neutron diagnostics ITER MCNP Neutron calibration Neutron flux monitor Neutron flux monitor ITER MCNP In-vessel neutron diagnostics Neutron calibration
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Summary:	•Neutron calibration experiments using a compact D-T neutron generator for ITER in-vessel neutron diagnostics have been simulated using MCNP with the simplified ITER model.•Angular neutron spectra from the compact D-T neutron generator have been evaluated for the source term of the MCNP calculation of the neutron calibration simulation.•Point efficiencies for an idealistic D-T neutron source have been calculated for NFM, DNFM, and MFC.•Point efficiency measurement using the compact D-T neutron generator facing NFM in EQ#1 is an effective method for the NFM calibration. The absolute calibration of the detection efficiency for the measurement of the total neutron yield in the whole plasma is one of the most important issues in neutron diagnostics. In ITER, a compact deuterium-tritium (D-T) neutron generator will be used as a neutron source for the neutron calibration prior to the D-T plasma experiments, where the neutron source will be moved in the vacuum vessel. Neutronic simulations of neutron diagnostic calibrations have been carried out for the strategy and scheduling of the calibration experiments. We have established a simplified 360° ITER model for the simulation, which includes neutron flux monitors (NFMs) in an equatorial port (EQ), micro fission chambers, diverter neutron flux monitors, and a neutron activation system. At first, angular neutron spectra of the compact D-T neutron generator have been evaluated by MCNP calculations. We evaluate the discrepancies among the detection efficiencies to be obtained by the neutron calibration experiment, those by idealistic D-T ring source, and actual detection efficiencies for the plasma neutron source. Point efficiency measurement using the compact D-T neutron generator facing NFM in EQ#1 is an effective method for the NFM calibration.
ISSN:	0920-3796 1873-7196
DOI:	10.1016/j.fusengdes.2023.113548