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

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10305 - Fluids and plasma physics (including surface physics)

Projekt

<a href="/cs/project/EF16_019%2F0000768" target="_blank" >EF16_019/0000768: COMPASS-U: Tokamak pro špičkový výzkum jaderné fúze</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Journal of Fusion Energy

ISSN

0164-0313

e-ISSN

1572-9591

Svazek periodika

41

Číslo periodika v rámci svazku

2

Stát vydavatele periodika

DE - Spolková republika Německo

Počet stran výsledku

11

Strana od-do

16

Kód UT WoS článku

000833963400001

EID výsledku v databázi Scopus

2-s2.0-85135373864