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Multiphysics approach to plasma neutron source modelling at the JET tokamak

机译:喷射托卡马克血浆中子源建模的多私人方法

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摘要

A novel multiphysics methodology for the computation of realistic plasma neutron sources has been developed. The method is based on state-of-the-art plasma transport and neutron spectrum calculations, coupled with a Monte Carlo neutron transport code, bridging the gap between plasma physics and neutronics. In the paper two JET neutronics tokamak models are used to demonstrate the application of the developed plasma neutron sources and validate them. Diagnostic data for the record JET D discharge 92436 are used as input for the TRANSP code, modelling neutron emission in two external plasma heating scenarios, namely using only neutral beam injection and a combination of the latter and ion cyclotron resonance heating. Neutron spectra, based on plasma transport results, are computed using the DRESS code. The developed PLANET code package is employed to generate plasma neutron source descriptions and couple them with the MCNP code. The effects of using the developed sources in neutron transport calculations on the response of JET neutron diagnostic systems is studied and compared to the results obtained with a generic plasma neutron source. It is shown that, although there are significant differences in the emissivity profiles, spectra shape and anisotropy between the neutron sources, the integral response of the time-resolved ex-vessel neutron detectors is largely insensitive to source changes, with major relative deviations of up to several percent. However it is calculated that, due to the broadening of neutron spectra as a consequence of external plasma heating, larger differences may occur in activation of materials which have threshold reactions located at DD neutron peak energies. The PLANET plasma neutron source computational methodology is demonstrated to be suitable for detailed neutron source effect studies on JET during DT experiments and can be applied to ITER analyses.
机译:已经开发出一种新的多体体方法,用于计算现实等离子体中子源的计算。该方法基于最先进的等离子体传输和中子谱计算,与蒙特卡罗中子传输码相结合,桥接等离子体物理学和中子学之间的间隙。在本文中,两种喷射中型托卡纳克模型用于证明所发育的等离子体中子源的应用并验证它们。记录射流D放电92436的诊断数据用作Transp码的输入,两个外部等离子体加热场景中的建模中子发射,即仅使用中性光束注射和后者和离子回旋谐振加热的组合。基于等离子体传输结果的中子谱是使用衣服代码计算的。开发的行星码包用于生成等离子体中子源描述并将其与MCNP代码耦合。研究了使用发射中子传输计算对喷射中子诊断系统的响应的效果,并与用通用等离子体中子源获得的结果进行比较。结果表明,尽管在中子源之间具有显着差异,但中子源之间的光谱形状和各向异性,但时间分辨的例血管中子探测器的积分响应在很大敏感对源变化的影响下,具有主要的相对偏差百分之几。然而,计算出,由于外部等离子体加热的结果扩大了中子谱,在具有位于DD中子峰能量的阈值反应的材料的激活中可能发生较大的差异。地球等离子体中子源计算方法被证明适用于DT实验期间射流的详细中子源效应研究,可以应用于浸渍分析。

著录项

  • 来源
    《Nuclear fusion》 |2019年第9期|096020.1-096020.20|共20页
  • 作者单位

    Jozef Stefan Inst Ljubljana Slovenia;

    Princeton Univ Princeton Plasma Phys Lab POB 451 Princeton NJ 08543 USA;

    Uppsala Univ Dept Phys & Astron Uppsala Sweden;

    Univ Nacl Educ Distancia Madrid Spain;

    United Kingdom Atom Energy Author Abingdon Oxon England;

    Ecole Polytech Fed Lausanne Swiss Plasma Ctr Lausanne Switzerland;

    Jozef Stefan Inst Ljubljana Slovenia;

  • 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 neutron source; Monte Carlo method; JET; TRANSP; DRESS; plasma transport;

    机译:等离子体中子源;蒙特卡罗方法;喷射;Transp;连衣裙;等离子运输;
  • 入库时间 2022-08-18 21:19:04

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