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A novel method for trace tritium transport studies

机译:痕量transport运输研究的新方法

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摘要

A new method combining a free-form solution for the neutron emissivity and the ratio method (Bonheure et al 2006 Nucl. Fusion 46 725-40) is applied to the investigation of tritium particle transport in JET plasmas. The 2D neutron emissivity is calculated using the minimum Fisher regularization method (MFR) (Anton et al 1996 Plasma Phys. Control. Fusion 38 1849, Mlynar et al 2003 Plasma Phys. Control. Fusion 45 169). This method is being developed and studied alongside other methods at JET. The 2D neutron emissivity was significantly improved compared with the first MFR results by constraining the emissivity along the magnetic flux surfaces. 1D profiles suitable for transport analysis are then obtained by subsequent poloidal integration.rnIn methods on which previous JET publications are based (Stork et al 2005 Nucl. Fusion 45 S181, JET Team (prepared by Zastrow) 1999 Nucl. Fusion 39 1891, Zastrow et al 2004 Plasma Phys. Control. Fusion 46 B255, Adams et al 1993 Nucl. Instrum. Methods A 329 277, Jarvis et al 1997 Fusion Eng. Des. 34-35 59, Jarvis et al 1994 Plasma Phys. Control. Fusion 36 219), the 14.07 MeV D-T neutron line integrals measurements were simulated and the transport coefficients varied until good fits were obtained. In this novel approach, direct knowledge of tritium concentration or the fuel ratio n_T_D is obtained using all available neutron profile information, e.g both 2.45 MeV D-D neutron profiles and 14.07 MeV D-T neutron profiles (Bonheure et al 2006 Nucl.Fusion 46 725-40). Tritium particle transport coefficients are then determined using a linear regression from the dynamic response of the tritium concentration n_T_D profile.rnThe temporal and spatial evolution of tritium particle concentration was studied for a set of JET discharges with tritium gas puffs from the JET trace tritium experiments. Local tritium transport coefficients were derived from the particle flux equation Γ=- D▽n_T + Vn_T where D is the particle diffusivity and V the convection velocity.rnTritium transport in the plasma core approaches the neoclassical level in some cases. For the set of plasmas analysed and within the uncertainty, tritium particle confinement follows the ITER IPB98(y,2) particle scaling confinement.
机译:一种将自由形式的溶液用于中子发射率和比率法相结合的新方法(Bonheure等人,2006 Nucl。Fusion 46 725-40)被用于研究J等离子体中in粒子的传输。使用最小Fisher正则化方法(MFR)计算2D中子发射率(Anton等人1996 Plasma Phys.Control。Fusion 38 1849,Mlynar等人2003 Plasma Phys.Control。Fusion 45169)。 JET正在与其他方法一起开发和研究该方法。通过限制沿磁通量表面的发射率,与第一个MFR结果相比,二维中子的发射率得到了显着提高。然后通过随后的多倍体积分获得适合于运输分析的一维剖面图。在以前的JET出版物所基于的方法中(Stork等2005 Nucl。Fusion 45 S181,JET Team(由Zastrow准备)1999 1999 Nucl。Fusion 39 1891,Zastrow等)等人2004 Plasma Phys.Control。Fusion 46 B255,Adams等人1993 Nucl.Instrum.Methods A 329277,Jarvis等人1997 Fusion Eng。Des.34-35 59,Jarvis等人1994 Plasma Phys.Control。Fusion 36219 ),对14.07 MeV DT中子线积分测量结果进行了模拟,并计算了输运系数,直到获得良好的拟合为止。在这种新颖的方法中,使用所有可用的中子剖面信息(例如2.45 MeV DD中子剖面和14.07 MeV DT中子剖面)都可以获得direct浓度或燃料比n_T / n_D的直接知识(Bonheure等人2006 Nucl.Fusion 46 725- 40)。然后从from浓度n_T / n_D分布的动态响应中使用线性回归来确定粒子的传输系数。rn研究了J气排放的一组JET放电中the气的concentration粒子浓度的时空变化,这些discharge气来自JET痕量tri实验。 the的局部输运系数由粒子通量方程Γ=-D▽n_T + Vn_T导出,其中D为粒子扩散率,V为对流速度。rn在某些情况下,等离子芯中的transport输运接近新古典水平。对于分析的等离子体集,并在不确定性范围内,tri粒子的约束遵循ITER IPB98(y,2)粒子尺度的约束。

著录项

  • 来源
    《Nuclear fusion》 |2009年第8期|234-244|共11页
  • 作者单位

    Laboratory for Plasma Physics, Association 'Euratom-Belgian State', Royal Military Academy,Avenue de la Renaissance, 30, Kunstherlevinglaan, B-1000 Brussels, Belgium;

    Association EURATOM-IPP.CR, Za Slovankou 3, CZ-180 00 Prague 8, Czech Republic;

    Consorzio RFX, Associazione ENEA-Euratom per la Fusione, Padova, Italy;

    Euratom/UKAEA Association, Culham Science Centre, Abingdon, Oxon, UK;

    Euratom/IST Fusion Association, Av Rovisco Pais, 1049-001, Lisbonne, Portugal;

    ITER Organisation, 13108 Saint-Paul-Lez-Durance, France;

    Euratom/UKAEA Association, Culham Science Centre, Abingdon, Oxon, UK;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    plasma diagnostic techniques and instrumentation; tokamaks; spherical tokamaks; tokamaks; spherical tokamaks;

    机译:血浆诊断技术和仪器;托卡马克球形托卡马克托卡马克球形托卡马克;
  • 入库时间 2022-08-18 00:45:12

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