Integrated core-SOL-divertor modelling for DEMO with tin divertor

Poradziński, M.; Ivanova‐Stanik, I.; Pełka, Grzegorz; Zagórski, R.

doi:10.1016/j.fusengdes.2017.04.131

Cited by 17 publications

(21 citation statements)

References 14 publications

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“…This is approximately the sensitivity limit of the NRA measurement, which is determined by the (small) background of about 0.01 counts/channel/µC in the relevant energy range that appears at higher 3 He energies. 4 He nuclear reaction analysis. The depth scale for these profiles corresponds to dense Sn equivalents.…”

Section: Liquid Snmentioning

confidence: 99%

“…Apart from lithium and low-melting eutectic alloys, also tin (Sn) has been suggested, since it promises a very low vapor pressure from the melting point at 505 K up to about 1000 K, as well as an endothermic solubility for hydrogen isotopes from the gas phase [1,3]. So far, experiments and computer simulations of liquid tin as plasma-facing material have focused mainly on the heat load handling capability and erosion of prospective components (see, e.g., [1,2,4]). Data on hydrogen isotope uptake in tin due to plasma irradiation is still very sparse; so far we only found three references for pure Sn [5,6,7].…”

Section: Introductionmentioning

confidence: 99%

“…Figure 7: D depth profiles in Sn obtained by D( 3 He, p)4 He nuclear reaction analysis. The depth scale for these profiles corresponds to dense Sn equivalents.…”

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confidence: 99%

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Deuterium retention in solid and liquid tin after low-temperature plasma exposure

et al. 2020

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Recently, plasma-facing components based on liquid metals were proposed for a prospective nuclear fusion reactor in order to circumvent challenges that occur for solid metal components, such as erosion lifetime, neutron embrittlement or transient overloading. One candidate material is liquid tin. We present a systematic study of the behavior of solid and liquid tin exposed to a lowtemperature deuterium plasma at temperatures between 300 and 515 K, focusing on deuterium retention and thermal release as well as on tin erosion and re-deposition. We find strong variations of deuterium depth profiles, release spectra, and erosion rates, which are correlated to dramatic changes in the surface morphology. In particular, we find evidence for massive gas bubble formation in tin, which can lead to the evolution of a thick, sponge-like layer for tin exposed to deuterium plasma just below the melting point, and to the rapid formation of a macroscopic gas pocket below liquid tin. We present evidence for strongly temperature-dependent chemical erosion of tin by deuterium plasma in the solid state. In the liquid state, a high tin erosion rate occurs, which is apparently induced by ejection of tin microdroplets. Furthermore, we observed strong plasmaassisted, low-temperature wetting of tin on tungsten near the melting point of tin. We tentatively propose the hypothesis that all of the observed effects may be influenced by tin-deuterium chemistry, e.g., the formation and de-composition of stannane molecules.

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Section: Liquid Snmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Deuterium retention in solid and liquid tin after low-temperature plasma exposure

et al. 2020

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“…In parallel with the research on the use of LM for the diverter, [15][16][17][18][19][20][21] the use of LM for the blanket has been extensively studied and, as one of the LM candidates for the blanket use, Sn-Bi(bismuth)-Li-Er(erbium) alloy (SBLE) has been considered. SBLE is mainly composed of Sn-Bi, which has a low melting point and is admixed with Li and Er; those are used for tritium breeder and stainless steel corrosion suppressor, respectively.…”

Section: Introductionmentioning

confidence: 99%

Bubbling phenomenon of liquidized Sn–Bi–Li–Er alloy under hydrogen plasma exposure

Tamura

Miyazawa²,

Masuzaki³

et al. 2022

Jpn. J. Appl. Phys.

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A laboratory-scale inductively coupled plasma apparatus investigated the behavior of liquid Sn–Bi–Li–Er alloy (SBLE) under hydrogen (H2) plasma exposure. By exposing the liquid SBLE to H2 plasma, the bubbling of liquid SBLE and pulsive H2 pressure increase were observed. Moreover, plasma density, i.e., ion flux, increased both bubble size and H2 pressure-spike. The simultaneous measurement of a high-speed camera and mass spectrometry concluded that the bubble was formed by H2 accumulation, and ~38% of hydrogen ion flux contributed to the H2 accumulation. Lithium hydride may be considered the bubble sphere’s origin from X-ray photoelectron spectroscopy measurement of droplets produced from the ruptured bubble sphere. From the experimental results, the bubble formation mechanism was discussed.

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“…The dependence of plasma current (Ip) and line averaged plasma density (<ne,line>) on R and BT are presented in Table I. In the simulations, 71.6% of the alpha power (Pα) heats the electrons and the remaining 28.4% the ions, as suggested in other papers [13,14], while the very important parameter ζ=D/χe, ratio between the particle and heat cross-field diffusion coefficients in the core is set to 0.35, as for the past COREDIV simulations [3,4,13]. Its magnitude determines the amount of the He ashes accumulation, and then that of the produced fusion power.…”

Section: Investigation With the Self-consistent Code Coredivmentioning

confidence: 99%

Analysis of the performances of a fusion reactor in a reduced H-mode confinement

et al. 2020

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The feasibility of a tokamak fusion reactor working in a reduced H-mode confinement, typical of the type III (or grassy) ELMs regime is here analyzed with two codes. The first is COREDIV that provides an integrated and self-consistent description of both the core and SOL plasma. The analysis is complemented by the 2D code TECXY which models the SOL more accurately and can then provide better estimates of the power deposited on the divertor targets. As for the present version of the EU DEMO, the auxiliary power is fixed at 50 MW and q95=3.5, while the energy confinement time is downgraded to 0.6 times the standard H-mode. The major radius R is increased by 1 m step from 9 up to 12 m and the toroidal magnetic field BT by 1 T step from 6 up to 8 T, with density kept at its Greenwald limit. An interesting working window around R=11 m and BT=7 is identified with the fusion gain Q≈30. The impurity seeding by either Xe or Kr, which can reduce the power input into the SOL and hence the load on the plates, can however affect the sustainment of the H mode, even if degraded. Argon is then considered for enhancing the radiated power inside the SOL. The TECXY analysis of this issue shows that the loads on to the target can be maintained at a very acceptable level, still preserving the core performance. Using liquid tin as divertor target material can be very advantageous for exhausting the power entering the divertor chamber provided argon is used in conjunction. In conclusion the option of a reactor working in a safer and simpler low confinement mode should not be put aside prematurely.

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Integrated core-SOL-divertor modelling for DEMO with tin divertor

Cited by 17 publications

References 14 publications

Deuterium retention in solid and liquid tin after low-temperature plasma exposure

Deuterium retention in solid and liquid tin after low-temperature plasma exposure

Bubbling phenomenon of liquidized Sn–Bi–Li–Er alloy under hydrogen plasma exposure

Analysis of the performances of a fusion reactor in a reduced H-mode confinement

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