Modelling of Neutron Markers for the COMPASS Upgrade Tokamak and Generation of Synthetic Neutron Spectra

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F22%3A00565692" target="_blank" >RIV/61389021:_____/22:00565692 - isvavai.cz</a>

Result on the web

<a href="https://link.springer.com/article/10.1007/s10894-022-00328-6" target="_blank" >https://link.springer.com/article/10.1007/s10894-022-00328-6</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1007/s10894-022-00328-6" target="_blank" >10.1007/s10894-022-00328-6</a>

Result language

angličtina

Original language name

Modelling of Neutron Markers for the COMPASS Upgrade Tokamak and Generation of Synthetic Neutron Spectra

Original language description

In the future COMPASS Upgrade (Vondracek et al. in Fusion Eng Des 169:112490, https://doi.org/10.1016/j.fusengdes.2021.112490, 2021) tokamak (R0=0.894m, Bt∼5T), three distinct types of edge transport barrier are anticipated: ELMy H-mode, EDA H-mode and I-mode. The main auxiliary heating system used to access H-mode will be Neutral Beam Injection (NBI) power. The NBI will have a nominal injection energy of 80keV at a maximum injection radius Rtan=0.6m. A significant neutron yield will occur from the interaction of the beam with the plasma background. Using our orbit-following code EBdyna (Jaulmes et al. in Nucl Fusion 61, 046012, https://doi.org/10.1088/1741-4326/abd41b, 2021), we calculate the trajectories of the NBI ions during the complete thermalization process, calculate the amount of NBI ions losses and evaluate the neutron rate in steady state from the beam–plasma and beam–beam interaction. Combining it with the thermal yield, we can derive detailed synthetic spectrogram of the energy distribution of the neutrons. The markers can be further used to provide synthetic neutron spectrometer diagnostics data. Due to the reduction of the simulated neutron count seen by the detectors when the peaking of the neutron source is lower, we anticipate the need for absolute-calibration in order to recover quantitative results.

Czech name

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Czech description

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Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

—

OECD FORD branch

10305 - Fluids and plasma physics (including surface physics)

Project

<a href="/en/project/EF16_019%2F0000768" target="_blank" >EF16_019/0000768: COMPASS-U: Tokamak for cutting-edge fusion research</a><br>

Continuities

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year

2022

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Name of the periodical

Journal of Fusion Energy

ISSN

0164-0313

e-ISSN

1572-9591

Volume of the periodical

41

Issue of the periodical within the volume

2

Country of publishing house

DE - GERMANY

Number of pages

11

Pages from-to

16

UT code for WoS article

000833963400001

EID of the result in the Scopus database

2-s2.0-85135373864