Triton burn-up study in JT-60U

Nishitani, T.; Hoek, M.; Harano, Hideki; Isobe, M.; Tobita, K.; Kusama, Y.; Wurden, G. A.; Chrien, R. E.

doi:10.1088/0741-3335/38/3/010

Cited by 45 publications

(41 citation statements)

References 9 publications

(10 reference statements)

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“…Because the field coils are discrete, the toroidal field in a tokamak is periodically corrugated or 'rippled'; the perturbation has a large toroidal mode number (typically n = 16-24) and a vertically symmetric poloidal perturbation (predominately m = 1). There have been numerous studies of the effect of toroidal field ripple on energetic ion confinement [1,[13][14][15][16][17][18][19]. Another extensively studied perturbation is the helical field that is resonant in the tokamak edge plasma (such as an n = 2, m = 7 perturbation (Ref.…”

Section: Introductionmentioning

confidence: 99%

The weak effect of static, externally imposed, helical fields on fusion product confinement in the DIII-D tokamak

et al. 2000

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Section: Introductionmentioning

confidence: 99%

The weak effect of static, externally imposed, helical fields on fusion product confinement in the DIII-D tokamak

et al. 2000

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“…Moreover, the radius of SciFi's circular active area, which consists of 91 scintillating fibres of each 1 mm diameter and 10 cm length, is calculated to be 0.477 cm. Taking the 15 • full-width half maximum viewing angle of the detector into account, [13] the geometrical fraction of the 10 12 s −1 14 MeV neutrons reaching the detector is about 10 4 s −1 . A considered position for SciFi at W7-X is in 8 m distance to the torus centre.…”

Section: F I G U R Ementioning

confidence: 99%

“…A plastic scintillating fibre detector, called SciFi, was developed and operated in the 1990s with the goal of detecting the energetic 14 MeV neutrons and determining triton burn-up as well as triton diffusion with temporal resolution in the order of 10 ms. [11][12][13][14] As the fibres are separated by aluminium and the scintillation light is detected by a photomultiplier tube using pulse height discrimination, this detector design features an intrinsic directionality and a gamma ray background suppression in the 14 MeV neutron signal even at high counting rates. [11] Recently, similar detectors were operated at LHD, yielding reasonable statistics for 14 MeV neutron rates above 10 12 s −1 .…”

mentioning

confidence: 99%

Estimation of 14 MeV neutron rate from triton burn‐up in future W7‐X deuterium plasma campaigns

Koschinsky

Äkäslompolo

Biedermann

et al. 2020

Contributions to Plasma Physics

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Fast ion confinement is of major importance for the ignition of a burning fusion plasma. In future deuterium plasma campaigns of the Wendelstein 7‐X stellarator, W7‐X, the amount of triton burn‐up is one possible measure for fast ion confinement. A well‐established technique to observe triton burn‐up is the 14 MeV neutron rate. In this paper, it is estimated whether an existing scintillating fibre neutron detector is also suited to measure triton burn‐up in W7‐X with sufficient accuracy. An estimation is presented, which can be applied to any tokamak or stellarator design and is one‐dimensional in the minor radius. The inputs are profiles of density, temperature, and differential volume element as well as the triton slowing‐down time. The estimation calculates the thermal deuteron fusion rate and the associated deuteron‐triton fusion rate; thus, the triton burn‐up generated 14 MeV neutron rate. It neither takes triton diffusion nor explicit losses into account. This thermally generated fusion rate is compared to the neutral beam injection heating induced beam‐plasma fusion rate.

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“…Semiconductor Si [9] and natural diamond (NDD) [10,11] detectors are also successfully used in counting mode for neutron flux monitoring in TFTR, JET (see Figure 1) and JT-60U. 14 MeV neutron detector based on scintillating fibers [12] was used for time-resolved triton bum-up measurements at JT-60U. Absolute calibration is the most important problem in neutron emission rate measurements.…”

Section: The Time-resolved Neutron Emission Rate Measurementsmentioning

confidence: 99%

Neutron and Gamma-ray Measurements

Krasilnikov

Sasao

Kiptily³

et al. 2008

AIP Conference Proceedings

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Due to high neutron and gamma-ray yields and large size plasmas many future fusion reactor plasma parameters such as fusion power, fusion power density, ion temperature, fuel mixture, fast ion energy and spatial distributions can be well measured by various fusion product diagnostics. Neutron diagnostics provide information on fusion reaction rate, which indicates how close is the plasma to the ultimate goal of nuclear fusion and fusion power distribution in the plasma core, which is crucial for optimization of plasma breakeven and burn. Depending on the plasma conditions neutron and gamma-ray diagnostics can provide important information, namely about dynamics of fast ion energy and spatial distributions during neutral beam injection, ion cyclotron heating and generated by fast ions MHD instabilities. The influence of the fast particle population on the 2-D neutron source profile was clearly demonstrated in JET experiments. 2-D neutron and gamma-ray source measurements could be important for driven plasma heating profile optimization in fusion reactors. To meat the measurement requirements in ITER the planned set of neutron and gamma ray diagnostics includes radial and vertical neutron and gamma cameras, neutron flux monitors, neutron activation systems and neutron spectrometers. The necessity of using massive radiation shielding strongly influences the diagnostic designs in fusion reactor, determines angular fields of view of neutron and gamma-ray cameras and spectrometers and gives rise to unavoidable difficulties in the absolute calibration. The development, testing in existing tokomaks and a possible engineering integration of neuron and gamma-ray diagnostic systems into ITER are presented.

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Triton burn-up study in JT-60U

Cited by 45 publications

References 9 publications

The weak effect of static, externally imposed, helical fields on fusion product confinement in the DIII-D tokamak

The weak effect of static, externally imposed, helical fields on fusion product confinement in the DIII-D tokamak

Estimation of 14 MeV neutron rate from triton burn‐up in future W7‐X deuterium plasma campaigns

Neutron and Gamma-ray Measurements

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