Neutronics analysis for integration of ITER diagnostics port EP10

Colling, Bethany; Eade, T.; Joyce, Malcolm J.; Pampin, R.; Seyvet, F.; Turner, Andrew; Udintsev, V. S.

doi:10.1016/j.fusengdes.2016.01.013

Cited by 11 publications

(9 citation statements)

References 5 publications

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“…The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports R. Juárez 1,a , J. Guirao 2 , A. Kolsek 1 , A. Lopez 1 , G. Pedroche 1 , L. Bertalot 2 , V.S. Udintsev 2 , M.J. Walsh 2 , P. Sauvan 1 and J. Sanz 1 VV, activating the port duct from outside the ports [5], which mitigation is in research [6]. Another reason is the insufficient reduction of the neutron flux transmission through the port plugs, the object of this work.…”

Section: Nuclear Fusionmentioning

confidence: 99%

“…They occupy about 75% of the port plug volume (see figure 2), while they must fit 53% of the weight limit (about 24 T to be shared by three of them). Their design to fulfil port plug weight compliance and radiation shielding demands is challenging, sometimes leading to port plug designs not meeting one or both of requirements [1].…”

Section: Nuclear Fusionmentioning

confidence: 99%

“…Depending on the port, the port plugs will host from 5 to 8 systems, commonly requiring apertures in the range of 100 cm 2 , subsequent doglegs and collimators. Given the large impacts of the penetrations in some examples [1,8], an initial guess for the drop is two orders of magnitude lower than the background. Studies focused on specific ports will refine the suggestion in future work.…”

Section: Propagation Of Sddr Limit To Dsm Designmentioning

confidence: 99%

“…This work is focused on the ITER diagnostics equatorial ports. During the current design phase, some examples of ports showing high SDDR are found [1,2].…”

Section: Introductionmentioning

confidence: 99%

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The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports

et al. 2018

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The ITER equatorial port plugs are submitted to a drained weight limit of 45 T. This limitation can conflict with their radiation shielding demands, although some weight margin is being discussed. The port interspaces are subject to a shutdown dose rate limit of 100 µSv h −1 after 10 6 s of cooling time. To meet it, the port plugs must show a neutron flux attenuation comparable to their neighborhood, despite considering penetrations to host systems. Most of this task relies on the drawer shield module (DSM). In this work, two DSM concepts are analyzed with this perspective: the box-based DSM and the modular DSM. Regardless the penetrations, the box-based DSM leads to unsatisfactory port plugs to meet both weight and SDDR requirements. On the contrary, the modular DSM shows a performance which allows for the adoption of such DSM concept, or equivalent, a port may comply with both requirements at the same time, provided the penetrations are well designed.

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Section: Nuclear Fusionmentioning

confidence: 99%

Section: Nuclear Fusionmentioning

confidence: 99%

Section: Propagation Of Sddr Limit To Dsm Designmentioning

confidence: 99%

“…This work is focused on the ITER diagnostics equatorial ports. During the current design phase, some examples of ports showing high SDDR are found [1,2].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports

et al. 2018

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“…As mentioned, the shielding properties of this design during plasma operation are sufficient. However, the shutdown dose rate, 10 6 s after plasma operation, is higher than the maximum permitted value of 100 µSv/h, which allows occasional access the interspace area [15,16]. These calculations show that with the LIDAR drawer the main contributions originate from the activation of the holder of mirror M1 and the 4 m long extension tube.…”

Section: Jinst 12 C12039mentioning

confidence: 99%

LIDAR TS for ITER core plasma. Part I: layout & hardware

Salzmann¹,

Gowers

Nielsen

2017

J. Inst.

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The original time-of-flight design of the Thomson scattering diagnostic for the ITER core plasma has been shown up by ITER. This decision was justified by insufficiencies of some of the components. In this paper we show that with available, present day technology a LIDAR TS system is feasible which meets all the ITER specifications. As opposed to the conventional TS system the LIDAR TS also measures the high field side of the plasma.The optical layout of the front end has been changed only little in comparison with the latest one considered by ITER. The main change is that it offers an optical collection without any vignetting over the low field side. The throughput of the system is defined only by the size and the angle of acceptance of the detectors. This, in combination with the fact that the LIDAR system uses only one set of spectral channels for the whole line of sight, means that no absolute calibration using Raman or Rayleigh scattering from a non-hydrogen isotope gas fill of the vessel is needed. Alignment of the system is easy since the collection optics view the footprint of the laser on the inner wall.In the described design we use, simultaneously, two different wavelength pulses from a Nd:YAG laser system. Its fundamental wavelength ensures measurements of 2 keV up to more than 40 keV, whereas the injection of the second harmonic enables measurements of low temperatures.As it is the purpose of this paper to show the technological feasibility of the LIDAR system, the hardware is considered in Part I of the paper. In Part II we demonstrate by numerical simulations that the accuracy of the measurements as required by ITER is maintained throughout the given plasma parameter range. The effect of enhanced background radiation in the wavelength range 400 nm–500 nm is considered. In Part III the recovery of calibration in case of changing spectral transmission of the front end is treated. We also investigate how to improve the spatial resolution at the plasma edge.

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