Power and isotope effects in the ITER baseline scenario with tungsten and tungsten-equivalent radiators in DIII-D

Journal Article · 06 June 2024 · Nuclear Fusion

DOI: https://doi.org/10.1088/1741-4326/ad4ef3 · OSTI ID:2427056

Sips, A. C. C.; Turco, F. ; Greenfield, C. M. ; Schmitz, L. ; Luce, T.; Odstrčil, T. ; McLean, A.; Bykov, I.; Hyatt, A.; Osborne, T.

Abstract Experiments in DIII-D document the ITER Baseline Scenario (IBS) at q ₉₅ ∼ 3 and P _IN / P _LH ∼ 1–2, in both deuterium and hydrogen utilizing Kr and Xe as Tungsten-equivalent radiators. The power threshold for H-mode operation ( P _LH ) was determined experimentally without added impurities and found to be about a factor of two higher than the scaling law. In recent IBS experiments in deuterium, intrinsic levels of metals such as Tungsten (W) or molybdenum and inconel are present that reduce the pedestal pressure by 20%–25%. A complete radiative collapse of deuterium IBS plasmas occurs at W core concentrations C _W = 10 ⁻⁵ . Simulations show that for core temperatures expected for ITER, the plasmas would not have a radiative collapse at C _W = 1 × 10 ⁻⁵ , moreover Q = 8–10 would still be achieved for C _W up to 3 × 10 ⁻⁵ . In contrast to deuterium, the IBS in hydrogen is not affected by intrinsic high-Z impurities, indicating that hydrogen H-modes in ITER may not inform the D-T phase with respect to W accumulation and discharge survival. Compared to deuterium, the pedestal pressure in hydrogen is ∼25% lower, with much higher ELM frequency of 150 Hz, decreasing with input power. Krypton was injected in a matrix scan of input power and impurity flow in IBS hydrogen discharges. Krypton impurity density profiles in hydrogen are similar to deuterium plasmas, but at Kr flows that are 2–3 times higher for the same input power. Krypton is transported into the core and affects the whole radius; at the highest injection rates a radiative collapse occurs at core radiation fractions of 0.3–0.35, consistent with the expected maximum W radiation fraction for ITER core plasmas. Comparing the results with previous International Tokamak Physics Activity database studies of the IBS confirms that at higher radiation fraction due to high-Z impurities, a drop in H ₉₈ of >10% is observed. On the other hand, the results using Kr as a W-equivalent radiator indicate that metal (W) devices at lower core temperatures than ITER may provide overly pessimistic performance extrapolations to ITER for deuterium-tritium operation. The new DIII-D results support a more attractive option for the ITER Research Plan with a short hydrogen phase for system commissioning, transitioning to deuterium operations as soon as possible to provide relevant conditions for deuterium-tritium operations.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: USDOE; USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
• Grant/Contract Number: AC52-07NA27344; FC02-04ER54698; FG02-04ER54761; SC0020287
• OSTI ID: 2427056
• Journal Information: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 7 Vol. 64; ISSN 0029-5515
• Publisher: IOP PublishingCopyright Statement
• Country of Publication: IAEA
• Language: English