Neutron emission from KSTAR Ohmically heated plasmas

England, A.C.; Lee, S.G.; Lee, Y.S.; Chen, Zhiyi; Yoo, J. W.; Kim, W.C.; Kwak, J. G.; Kwon, M.

doi:10.1016/j.physleta.2011.06.065

Cited by 6 publications

(2 citation statements)

References 13 publications

(14 reference statements)

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“…In addition to the fluctuation diagnostics, a set of energetic particle diagnostics such as the neutron detector [44,45] and the fast-ion loss detector (FILD) [46] have been used to investigate the impact of Alfvénic activities on fast-ion transport. The neutron detectors used in this experiment are based on the NE213 [45] or stilbene scintillators, which are calibrated with the measurements from the ITER-prototype neutron activation system [47,48] and TRANSP [49] modelling.…”

Section: Heating Current Drive and Diagnosticsmentioning

confidence: 99%

Suppression of toroidal Alfvén eigenmodes by the electron cyclotron current drive in KSTAR plasmas

et al. 2022

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Advanced operation scenarios such as high poloidal beta (βP) or high q min are promising concepts to achieve the steady-state high-performance fusion plasmas. However, those scenarios are prone to substantial Alfvénic activity, causing fast-ion transport and losses. Recent experiments with the advanced operation scenario on KSTAR tokamak have shown that the electron cyclotron current drive (ECCD) is able to mitigate and suppress the beam-ion driven toroidal Alfvén eigenmodes (TAEs) for over several tens of global energy confinement time. Co-current directional intermediate off-axis ECCD lowers the central safety factor slightly and tilts the central q-profile shape so that the continuum damping in the core region increases. Besides, the rise of central plasma pressure and increased thermal-ion Landau damping contribute to TAE stabilization. While the TAEs are suppressed, neutron emission rate and total stored energy increase by approximately 45% and 25%, respectively. Fast-ion transport estimated by TRANSP calculations approaches the classical level during the TAE suppression period. Substantial reduction in fast-ion loss and neutron deficit is also observed. Enhancement of fast-ion confinement by suppressing the TAEs leads to an increase of non-inductive current fraction and will benefit the sustainment of the long-pulse high-performance discharges.

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Section: Heating Current Drive and Diagnosticsmentioning

confidence: 99%

Suppression of toroidal Alfvén eigenmodes by the electron cyclotron current drive in KSTAR plasmas

et al. 2022

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“…Neutrons from Ohmically heated KSTAR plasmas were detected for the first time in 2010 using a sensitive 3 He detector, although the relation between measured neutron rate and D-D reaction rate was not identified clearly [2]. New neutron diagnostic systems such as a fission chamber, stilbene spectrometers, and a neutron activation system have been installed at KSTAR for more accurate detection of neutrons from the KSTAR plasmas.…”

Section: Introductionmentioning

confidence: 99%

Diagnostic neutron activation system for KSTAR

et al. 2012

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The Korea Superconducting Tokamak Advanced Research (KSTAR) device has begun deuterium plasma operation and increased neutron generation from D-D fusion reaction in the plasma is expected as the heating power of the plasma increases. A neutron activation system utilizing the pneumatic transfer of encapsulated metal samples has been implemented to monitor the fusion neutron source strength and the total fusion power from the KSTAR plasma. The prototype pneumatic transfer system for the ITER neutron activation system was slightly modified to be used for KSTAR, and a High Purity Germanium (HPGe) detection system was used to count gamma photons from the activated samples. The Monte Carlo code MCNP and the inventory code FIS-PACT were also used for the calculations to evaluate the total number of neutrons emitted from the D-D fusion reactions in the KSTAR plasma. The analysis of data from an activation measurement obtained from the 2011 KSTAR campaign shows the neutron flux at the irradiation station was 2.2×10 8 cm −2 s −1 , and the total neutron yield was 4.7×10 13 n/s for a typical NBI-heated, H-mode KSTAR plasma shot. KEYWORDS: Nuclear instruments and methods for hot plasma diagnostics; Neutron detectors (cold, thermal, fast neutrons)

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