Experimental Check of Deceleration of Neutral Beam-Injected Energetic Ions in the HL-2A Tokamak

Isobe, M.; Liu, Yi; Yuan, Guoliang; Zhang, Yipo; Yang, Jinwei; Chen, Wei; Yang, Qingwei; Duan, X.R.; Morita, S.; Toi, K.

doi:10.1585/pfr.6.2402107

Cited by 4 publications

(3 citation statements)

References 11 publications

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“…In the pulse counting mode, an abrupt increase in the neutral beam injection (NBI) power will cause a neutron flux jump from low level to high level, causing serious signal pileups at this time [16][17][18][19]. If the pulse counting mode is still being used, serious errors will occur in the measurement and cause the upper-level control system to make erroneous judgment on the work status of the tokamak.…”

Section: Data Processing Algorithmsmentioning

confidence: 99%

A digital wide range neutron flux measuring system for HL-2A

Yuan

Yin

2017

Plasma Sci. Technol.

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To achieve wide-range, high-integration, and real-time performance on the neutron flux measurement on the HL-2A tokamak, a digital neutron flux measuring (DNFM) system based on the peripheral component interconnection (PCI) eXtension for Instrumentation express (PXIe) bus was designed. This system comprises a charge-sensitive preamplifier and a field programmable gate array (FPGA)based main electronics plug-in. The DNFM totally covers source-range and intermediate-range neutron flux measurements, and increases system integration by a large margin through joining the pulse-counting mode and Campbell mode. Meanwhile, the neutron flux estimation method based on pulse piling proportions is able to choose and switch measuring modes in accordance with current flux, and this ensures the accuracy of measurements when the neutron flux changes suddenly. It has been demonstrated by simulated signals that the DNFM enhances the full-scale measuring range up to 1.9×10 8 cm −2 s −1 , with relative error below 6.1%. The DNFM has been verified to provide a high temporal sensitivity at 10 ms time intervals on a single fission chamber on HL-2A.

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Section: Data Processing Algorithmsmentioning

confidence: 99%

A digital wide range neutron flux measuring system for HL-2A

Yuan

Yin

2017

Plasma Sci. Technol.

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“…Energetic ion confinement has been studied in HL-2A using a neutron flux monitor, a radial neutron camera [16], and a fastion loss detector [17,18]. The classical confinement of beam ions and the loss of beam ions due to magnetohydrodynamics instabilities were studied [19][20][21][22][23][24]. Based on the knowledge of HL-2A, energetic particle confinement studies will be performed in HL-2M using comprehensive neutron diagnostics.…”

Section: Introductionmentioning

confidence: 99%

Predictive analysis for triton burnup ratio in HL-2A and HL-2M plasmas

Ogawa¹,

Zhang²,

Zhang³

et al. 2021

Plasma Phys. Control. Fusion

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The expected triton burnup ratio was analyzed based on numerical simulation to study the feasibility of demonstrating energetic particle confinement through 1 MeV triton burnup experiments in HL-2A and HL-2M. Calculations were conducted using LORBIT, a collisionless Lorentz orbit code, and FBURN, a neutron emission calculation code based on the classical confinement of energetic particles. First, the orbit loss and radial distribution of the tritons were evaluated using the LORBIT code. The LORBIT code revealed that all tritons were lost within ∼10−6 s in HL-2A, whereas in HL-2M, most of the tritons were still confined at 10−3 s. The FBURN code calculated the deuterium–tritium neutron emission rate using the radial distribution of 1 MeV tritons. The predictive analysis found that nearly no deuterium–tritium neutrons remained in HL-2A at a plasma current of 160 kA. Also, in HL-2M, a significant triton burnup ratio could be obtained at the relatively high plasma currents of 1MA, 2MA, and 3MA. This analysis predicts that the triton burnup ratio exceeds 1% under relatively high plasma current conditions.

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“…The fission chamber has good characteristic curves for the voltage and counting plateaus. It was installed on HL-2A for D-D fusion neutron flux monitoring [8,9] . In this study, two fission chamber prototypes have been manufactured and the high bias plateau and the characteristics of pulse height have been tested.…”

Section: Introductionmentioning

confidence: 99%

Fusion Neutron Flux Detector for the ITER

Yuan¹,

Qi²,

Yang³

et al. 2014

Plasma Sci. Technol.

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Two fission chambers with different amounts of fissile material (enriched 90% uranium-235) have been manufactured for neutron flux detection in a thermonuclear fusion device. The characteristics of neutron signal and its discrimination from other signals, and a plateau of high voltage between the anode and cathode have been validated in a thermal neutron source. The energy responses of the two fission chambers at seven energy levels have been calibrated in an accelerator fast neutron source and the results agree well with the simulations.

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Experimental Check of Deceleration of Neutral Beam-Injected Energetic Ions in the HL-2A Tokamak

Cited by 4 publications

References 11 publications

A digital wide range neutron flux measuring system for HL-2A

A digital wide range neutron flux measuring system for HL-2A

Predictive analysis for triton burnup ratio in HL-2A and HL-2M plasmas

Fusion Neutron Flux Detector for the ITER

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