Design Features of the Neutral Particle Diagnostic System for the ITER Tokamak

The control of the deuterium–tritium (DT) fuel isotopic ratio has to ensure the best performance of the ITER thermonuclear fusion reactor. The diagnostic system described in this paper allows the measurement of this ratio analyzing the hydrogen isotope fluxes (performing neutral particle analysis (NPA)). The development and supply of the NPA diagnostics for ITER was delegated to the Russian Federation. The diagnostics is being developed at the Ioffe Institute. The system consists of two analyzers, viz., LENPA (Low Energy Neutral Particle Analyzer) with 10–200 keV energy range and HENPA (High Energy Neutral Particle Analyzer) with 0.1–4.0MeV energy range. Simultaneous operation of both analyzers in different energy ranges enables researchers to measure the DT fuel ratio both in the central burning plasma (thermonuclear burn zone) and at the edge as well. When developing the diagnostic complex, it was necessary to account for the impact of several factors: high levels of neutron and gamma radiation, the direct vacuum connection to the ITER vessel, implying high tritium containment, strict requirements on reliability of all units and mechanisms, and the limited space available for accommodation of the diagnostic hardware at the ITER tokamak. The paper describes the design of the diagnostic complex and the engineering solutions that make it possible to conduct measurements under tokamak reactor conditions. The proposed engineering solutions provide a safe—with respect to thermal and mechanical loads—common vacuum channel for hydrogen isotope atoms to pass to the analyzers; ensure efficient shielding of the analyzers from the ITER stray magnetic field (up to 1 kG); provide the remote control of the NPA diagnostic complex, in particular, connection/disconnection of the NPA vacuum beamline from the ITER vessel; meet the ITER radiation safety requirements; and ensure measurements of the fuel isotopic ratio under high levels of neutron and gamma radiation.     

Installation and Primary Results of a Neutral Particle Analyzer on HL-2A Tokamak

The target of nuclear fusion research is to realize effective and sustainable fusion reaction of hydrogen isotope ions and to get the thermonuclear energy economically. Naturally the parameters of plasma ions are of importance and measurement of the parameters of ions has been an essential concern to the nuclear fusion research work since 1950s. However, the ions are confined by the mag- netic field, one can measure the neutral particles emitting from the plasma to obtain the parameters of ions. The diagnosing of neutral particles is a method by measuring the neutral particles from the plasma to obtain the information （such as energy） of ions, and it is important and foundational to the experi ments as well.     

Spectroscopic Diagnostic of the Peripheral Plasma in the Globus-M2 Tokamak with the Injection of Neutral Helium

JETP Letters - The diagnostic of the peripheral plasma parameters in terms of the relation of lines of neutral helium is included in the diagnostic complex of the tokamak Globus-M2. The first...     

The Influence of Neutral Particle Sources on the Dynamics of Tokamak Plasmas. II. Particle Dynamics and Induced Electromagnetic Fields

In part I of our paper [1] a kinetic theory of the influence of neutral particle sources on the dynamics of tokamak plasmas has been developed and the general solution of this problem has been given for an arbitrary source function. By the use of these results we calculate in this part II the particle's distribution function for different simple source functions. In the case of recycling perpendicular to the limiter surface we derive analytical expressions for the charge density, the induced electric potential and the anomaleous electron density flux transverse to the magnetic field.     

Beam Ion Transport from Neutron Emissivity Measurement in Deuterium Neutral Beam-Heated Deuterium Plasmas of the HL-2A Tokamak

An experiment at the HL-2A tokamak with a high-energy deuterium neutral beam （NB） injection （30 keV, about 0.6 MW） was performed. The emission of d-d fusion neutrons dominated by beam-plasmas reactions when the deuterium NB was injected into the deuterium target plasma was observed by means of a ^235U fission chamber. To obtain information on NB deposition and the slowing down of beam ions in HL-2A plasmas, a very short-pulse deuterium NB injection, or the so-called ＂blip＂ injection, was performed into MHD-quiescent Ohmic deuterium plasmas. Analysis of neutron decay following the NB ＂blip＂ injection indicates that tangentially injected beam ions are well confined, slowing down classically in the HL-2A. In contrast to the MHD-quiescent plasma, anomalous losses of beam ions were observed when tearing mode instabilities were present.     

Estimation of Charge Exchange Recombination Emission Based on Diagnostic Neutral Beam on the Experimental Advanced Superconducting Tokamak

Diagnostic neutral beam （DNB） attenuation and charge exchange recombination emission are estimated on EAST tokamak. Approximately 40% of the beam with the energy of 50 keV can reach the plasma centre （r = 0） for the typical parameters of the Experimental Advanced Superconducting Tokamak （EAST） plasma. Emissivities of CVI （n = 8 → 7, 529.0nm） and OVⅢ （n = 10 →9, 607.Ohm） visible charge exchange recombination emissions based on the DNB are estimated. The emissivities of the visible bremsstrahlung emission near this wavelength are also calculated for comparison. The results show that the charge exchange recombination emission is about two orders of magnitude greater than the bremsstrahlung emission. It is theoretically indicated that the ratio of signal of charge exchange recombination spectroscopy to the noise from background bremsstrahlung emission, S/N, is large enough in the EAST tokamak with the typical designed parameters. The present results are helpful for experiment design of charge-exchange recombination spectroscopy based on the DNB in the EAST tokamak.     

The Sawtooth Oscillation Effect on Fast-Ion Energy Spectra in ITER Plasma and Neutral Particle Analyzer Measurements

ITER plasma with parameters close to those with the inductive scenario is considered. The distribution functions of fast ions of deuterium D and tritium T are calculated while taking into account the elastic nuclear collisions with alpha particles ⁴He using the code FPP-3D. The D and T energy spectra detected by the neutral-particle analyzer (NPA) are determined. The plasma mixing effect on these spectra during sawtooth oscillations is studied. It is shown that the NPA makes it possible to detect sawtooth plasma oscillations in ITER and determine the percentage composition of the D?T mixture in it both with the presence of instabilities and without them. A conclusion is drawn on the prospects of using NPA data in automatic controllers of thermonuclear fuel isotopic composition control and plasma oscillation regulation in ITER.     

Numerical Modelling of Impurity Retention in the ITER Tokamak Scrape-off Layer Plasma

The hydrogen plasma and carbon ions flows generated at the target plates in the ITER tokamak scrape-off layer are numerically investigated. A 2D model of hydrogen plasma and impurity ions is presented. The model is based on the electron-ion Braginski fluid equations [1] for hydrogen plasma and rate equations for impurities. Arbitrary level of impurity ions concentration is assumed. Recycling of hydrogen, sputtering and self sputtering of carbon atoms at the target plates are taken into account. Equations of the model are solved in the slab geometry using 2D-multifluid numerical code EPIT [2]. Problems of impurity ions retention and radiation in the divertor volume are analyzed. Results of calculations for ITER tokamak boundary plasma are presented, showing that poor retention is likely at high impurity concentration in the divertor volume. The radiation power can be a significant part of ingoing energy.     

A Study of the Influence of Misalignment on Measuring Results for Laser Particle Analyzers

Light scattering-based laser particle analyzers have found wide use in powder technology and many-particle systems. It is very important that the photodetector of the analyzer is in good alignment with the incident laser beam, otherwise errors will occur. In this paper, the influences of misalignment on the final results of measurements are discussed.     

H.V. Power Supplies for Tokamak Neutral Beam Injectors

Neutral Beam Injectors need HV power to accelerate the ions produced by the ion sources. To satisfy future demands for higher voltages and currents a modular design is necessary to obtain the required values by series/parallel operation of modules. A survey is given of properties and possibilities. Apart from regulating transformers and thyristors for voltage control a tetrode in the primary circuit is considered as an attractive alternative.     

Concept of Plasma Heating and Current Drive Neutral Beam System for Fusion Neutron Source DEMO-FNS

Steady-state operation of a fusion neutron source (FNS) requires plasma heating and current drive by means of additional power delivered by neutral beams. Six neutral beam injectors (NBI) will provide the DEMO-FNS machine with additional heating power up to 30 MW, with neutral particle energy of 500 keV. NBI systems developed for ITER can serve as the prototype for DEMO-FNS, as both systems have similar ion source current, with accelerated beam power in ITER NBI (1MeV) being twice as large as in DEMOFNS. The paper describes the NBI system with account of its integration into DEMO-FNS tokamak complex.     

Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion–Fission Transmutation System

A sub-critical advanced reactor based on Tokamak technology with a D–T fusion neutron source is an innovative type of nuclear system. Due to the large number of neutrons produced by fusion reactions, such a system could be useful in the transmutation process of transuranic elements (Pu and minor actinides (MAs)). However, to enhance the MA transmutation efficiency, it is necessary to have a large neutron wall loading (high neutron fluence) with a broad energy spectrum in the fast neutron energy region. Therefore, it is necessary to know and define the neutron fluence along the radial axis and its characteristics. In this work, the neutron flux and the interaction frequency along the radial axis are evaluated for various materials used to build the first wall. W alloy, beryllium, and the combination of both were studied, and the regions more suitable to transmutation were determined. The results demonstrated that the best zone in which to place a transmutation blanket is limited by the heat sink and the shield block. Material arrangements of W alloy/W alloy and W alloy/beryllium would be able to meet the requirements of the high fluence and hard spectrum that are needed for transuranic transmutation. The system was simulated using the MCNP code, data from the ITER Final Design Report, 2001, and the Fusion Evaluated Nuclear Data Library/MC-2.1 nuclear data library.     

蒙特卡罗粒子输运计算自动建模程序MCAM在ITER核分析建模中的应用

国际热核试验堆（ITER）核分析的主要计算工具是三维蒙特卡罗输运程序MCNP。MCAM（MCNP Auto-Modeling system）作为MCNP自动建模与可视化软件,其主要功能是CAD模型与MCNP计算模型之间的数据交互。一方面MCAM可将通用格式的CAD模型转换成MCNP计算模型,另一方面作为一个可视化工具,它可以以CAD模型的方式显示MCNP计算模型中几何及材料等相关信息。主要介绍利用MCAM对ITER三维MCNP模型的改进,主要包括:包层模块的重建和内包层几何细化;模型环向角度从20°到40°的扩展。In order to conduct nuclear analyses on neutronics issues for ITER （International Thermonuclear Experimental Reactor）, a standard three-dimensional model of the ITER reactor is being developed. The complex nuclearanalyses are conducted by MCNP/4C in three dimensions. MCAM （MCNP Auto-Modeling system） , as an implementation of the interface code between modern CAD system and MCNP, is a modeling and visualization tool which can convert a CAD model to neutronics model for MCNP and vice versa. This paper presents the application of MCAM to modify ITER 3-D neutronics model, which include blanket segmentation update, incorporation of fine structures of inboard blanket and the model extension from 20° to 40° in toroidal direction     

Vacuum System for HL-2A Tokamak

The vacuum system of today＇s tokamak devices is designed to meet the operational requirements of the experiments. The operation can be divided into five modes, （1） pumping down and leak detecting of the vacuum vessel, （2） baking, （3） plasma-facing component （PFC） conditioning, （4）evacuating and controlling of the particles at plasma edge, （5） plasma discharge experiments.     

汤姆逊散射技术在HL-2A装置上的应用进展

非相干激光汤姆逊散射诊断只需要假设电子速度满足Maxwell分布,测量得到的等离子体电子温度与电子密度的数据准确可靠,是托卡马克和其他磁约束核聚变研究装置上重要的诊断工具,并朝着高可靠性、高空间分辨和高重复测量频率的方向发展,其中高可靠性是前提。电子的汤姆逊散射截面很小,其总截面为σ_T=6.65×10^-25 cm²,通常使用电光调Q的Nd∶YAG激光器作为散射光源,激光脉冲宽度约10 ns、脉冲能量约3 J,用5～8通道的光谱仪对散射光谱进行测量与分析。如何对光电探测模块输出的散射脉冲进行数据采集,是激光散射诊断的关键问题之一。以前使用电流积分式的数据采集器(Q-ADCs,如CMC080模块),在一个确定的时间宽度(如50 ns)将散射脉冲信号积分在采样电容器上,从而得到散射信号的强度值,这种方法很难排除电路噪声和外来干扰。该研究通过使用高速数据采集器(纵向分辨率≥10 bits、采样频率f≥1 GS·s^-1,如V1742B模块)在包含散射信号在内的时间段(如300～500 ns)进行采集,获得散射...     

Calibration of ITER Instant Power Neutron Monitors: Recommended Scenario of Experiments at the Reactor

Instant power is a key parameter of the ITER. Its monitoring with an accuracy of a few percent is an urgent and challenging aspect of neutron diagnostics. In a series of works published in Problems of Atomic Science and Technology, Series: Thermonuclear Fusion under a common title, the step-by-step neutronics analysis was given to substantiate a calibration technique for the DT and DD modes of the ITER. A Gauss quadrature scheme, optimal for processing “expensive” experiments, is used for numerical integration of ²³⁵U and ²³⁸U detector responses to the point sources of 14-MeV neutrons. This approach allows controlling the integration accuracy in relation to the number of coordinate mesh points and thus minimizing the number of irradiations at the given uncertainty of the full monitor response. In the previous works, responses of the divertor and blanket monitors to the isotropic point sources of DT and DD neutrons in the plasma profile and to the models of real sources were calculated within the ITER model using the MCNP code. The neutronics analyses have allowed formulating the basic principles of calibration that are optimal for having the maximum accuracy at the minimum duration of in situ experiments at the reactor. In this work, scenarios of the preliminary and basic experimental ITER runs are suggested on the basis of those principles. It is proposed to calibrate the monitors only with DT neutrons and use correction factors to the DT mode calibration for the DD mode. It is reasonable to perform full calibration only with ²³⁵U chambers and calibrate ²³⁸U chambers by responses of the ²³⁵U chambers during reactor operation (cross-calibration). The divertor monitor can be calibrated using both direct measurement of responses at the Gauss positions of a point source and simplified techniques based on the concepts of equivalent ring sources and inverse response distributions, which will considerably reduce the amount of measurements. It is shown that the monitor based on the average responses of the horizontal and vertical neutron chambers remains spatially stable as the source moves and can be used in addition to the staff monitor at neutron fluxes in the detectors four orders of magnitude lower than on the first wall, where staff detectors are located. Owing to low background, detectors of neutron chambers do not need calibration in the reactor because it is actually determination of the absolute detector efficiency for 14-MeV neutrons, which is a routine out-of-reactor procedure.