Comparative study of boron and neon injections on divertor heat fluxes using SOLPS-ITER simulations

Based on the EAST equilibrium,the effects of boron(B)and neon(Ne)injected at different locations on the target heat load,and the distributions of B and Ne particles were investigated by transport code SOLPS-ITER.It was found that the B injection was more sensitive to the injection location for heat flux control than impurity Ne.The high electron and ion densities near the inner target in the discharge with impurity B injected from over X-point(R1)led to plasma detachment only at the inner target,and the localized B ions in the cases with injection from outer target location(R2)and upstream location(R3)led to far-SOL detachment at the outer target,but not at the inner target.In contrast,for Ne,the spatial distributions of Ne ions and electrons were found to be similar in all the cases at the three injection locations,and the detached plasma was achieved at the inner target and the electron temperature was reduced at the outer target.For locations R2 and R3,impurity B showed a more pronounced effect on the heat flux at the far-SOL of the outer target.Further analysis indicated that Ne atoms came mainly from the recycling sources,whereas B atoms came mainly from injection,and that their distinct atomic distributions resulted from the difference in the ionization threshold and ionization mean free path.In addition,the radiation proportion of B in the divertor region was larger than that of Ne when the total radiation power was similar,which suggests that B has less influence on the core region.

ITER氦冷固态增殖剂试验包层模块中子学设计与优化

针对ITER中国氦冷固态增殖剂试验包层模块(HCCB TBM)的概念设计方案进行了初步中子学设计和优化。在铍球床填充率从80%降为62%的情况下,通过调整TBM内部结构的材料和布置,提出了一种中子学性能更好且满足安全要求的设计方案。计算结果表明,优化后HCCB TBM的产氚率比概念设计值提高的满功率运行一天后的产氚量为0.42mg,但总核热和最大功率密度有了一定降低。

Static Structural Analysis for a Neutron Shielding Block in ITER

The ITER neutron shielding blocks are located between the outer shell and the inner shell of the vacuum vessel to provide neutron shielding. Considering the combined loads acting on the shielding blocks during ITER plasma operation, the structure of the shielding blocks must be evaluated. Using the finite element method with ANSYS analysis software, static structural analysis is performed, including elastic analysis and limit analysis for one typical shielding block. The evaluated results based on RCC-MR code show that the structure of this shielding block can meet the design requirement.

Nuclear Safety Functions of ITER Gas Injection System Instrumentation and Control and the Concept Design

The ITER Gas Injection System（GIS） plays an important role on fueling, wall conditioning and distribution for plasma operation. Besides that, to support the safety function of ITER, GIS needs to implement three nuclear safety Instrumentation and Control（I＆C） functions.In this paper, these three functions are introduced with the emphasis on their latest safety classifications. The nuclear I＆C design concept is briefly discussed at the end.

ITER Magnet Feeder:Design,Manufacturing and Integration

The International Thermonuclear Experimental Reactor （ITER） feeder procurement is now well underway. The feeder design has been improved by the feeder teams at the ITER Organization （IO） and the Institute of Plasma Physics, Chinese Academy of Sciences （ASIPP） in the last 2 years along with analyses and qualification activities. The feeder design is being progressively finalized. In addition, the preparation of qualification and manufacturing are well scheduled at ASIPP. This paper mainly presents the design, the overview of manufacturing and the status of integration on the ITER magnet feeders.

Conceptual Design of the ITER Gas Injection System

A conceptual design review of the ITER gas injection system （GIS） function, safety, operation, and maintenance has recently been successfully completed. The GIS design can now continue to the preliminary design stage. This paper gives an overall description of the requirements and implementation at the concept design level. The designs of the sub-systems according to its breakdown structure are discussed against the corresponding requirements.

Design Evolution and Analysis of the ITER Cryostat Support System

The cryostat is a vacuum tight container enveloping the entire basic systems of the ITER tokamak machine,including a vacuum vessel,a superconducting magnet and thermal shield etc.It is evacuated to a pressure of 10^-4Pa to limit the heat transfer via gas conduction and convection to the cryogenically cooled components.Another important function of cryostat is to support all the loads from the tokamak to the concrete floor of the pit by its support system during different operational regimes and accident scenarios.This paper briefly presents the design evolution and associated analysis of the cryostat support system and the structural interface with the building.

3D electromagnetic simulation of the coupling characteristics and double-stub Ferrite tuners impedance matching for EAST ICRH four-strap antenna

A program developed with COMSOL software integrates EAST four-strap antenna coupling with the double-stub Ferrite tuners(FT)impedance matching,obtaining physical quantities crucial for predicting the overall performance of the ion cyclotron resonance heating(ICRH)antenna and matching system.These quantities encompass S-matrix,port complex impedance,reflection coefficients,electric field and voltage distribution,and optimal matching settings.In this study,we explore the relationship between S-matrix,reflection coefficients,port complex impedance,and frequency.Then,we analyze the impact of Faraday screens placement position and transparency,the distance from the Faraday screen(FS)to the current straps(CS),the relative distance between ports,and the characteristic impedance of the transmission line on the coupling characteristic impedance of the EAST ICRH system.Finally,we simulate the electric field distribution and voltage distribution of the EAST ICRH system for plasma heating with double-stub FT impedance matching.Using optimized parameters,the coupling power of the ICRH system can be approximately doubled.The results present herein may offer guidance for the design of high-power,long-pulse operation ICRH antenna systems.

The tri-band high spectral resolution spectrometer with gratings in tandem for the charge-exchange recombination spectroscopy diagnostic system on HL-2A tokamak

Charge-exchange(CX) recombination spectroscopy is a powerful tool monitoring ion temperature and plasma rotation with good temporal and spatial resolutions. A compact, new design for a high-throughput, tri-band high spectral resolution spectrometer has been developed for the charge-exchange recombination spectroscopy measurement on the HL-2A tokamak. The simultaneous measurements of He II(468.57 nm), C VI(529.1 nm), and Dα(656.1 nm accompanied by beam emission spectra) with an acquisition frequency up to 400 Hz are achieved by vertically binning the spectrum from each fiber in experiments. Initial results indicate that the system can provide radial profiles of not only ion temperature and rotation velocity,but also concentration of carbon. For the case of helium, the measurements for the ion temperature and rotation velocity are straightforward but the apparent concentration associated with the observed CX intensity is obviously too high. Modeling of the active He II CX feature including plume contributions needs to be carried out to extract the true helium concentration.The spectrometer could become a prototype for the ITER charge-exchange recombination spectroscopy diagnostic and the pilot experiments, as presented here, demonstrate the possibility of impurity concentrations measurements based on the combined measurement of local beam emission and charge-exchange recombination spectroscopy spectra.

中国氦冷固态增殖剂试验包层模块系统活化计算分析

基于中国氦冷固态增殖剂试验包层模块(CN HCCB TBM)的最新设计方案和ITER提供的中子学基准模型C-lite,采用国际通用的Monte Carlo粒子输运程序MCNP和欧洲活化程序FISPACT-2007对HCCB TBM及其辅助系统(统称为HCCB TBS)进行了详细的活化计算分析,得到并讨论了各结构部件的放射性、余热和接触剂量率结果。结果表明,停堆时HCCB TBM模块的总放射性和总余热分别为2.348×1016 Bq和5.826 k W。活化计算结果可以为TBS的安全分析、维护和放射性废物处置等提供数据基础和分析依据。

超导托卡马克EAST限制器材料的腐蚀与沉积的研究

在磁约束聚变实验装置托卡马克中,第一壁材料直接面对高温等离子体,承受高能粒子的轰击。随着聚变装置等离子体存在时间的延长及辅助加热功率的增加,第一壁材料腐蚀和沉积将会越来越严重。材料的腐蚀一方面会污染等离子体影响聚变等离子体的品质,另一方面将危害装置的安全运行。为了提高材料的物理和化学溅射阈值,超导托卡马克东方超环(EAST)装置上选用掺杂碳化硅涂层石墨作为第一壁材料。本实验通过离子束表面分析方法,研究了EAST装置中限制器石墨材料的腐蚀与沉积特性,结果显示在累计大约36000s的等离子体实验中,安装在限制器上的标记瓦块近1μm的碳涂层基本被腐蚀,其腐蚀速率超过0.0278 nm/s。

Design of Tokamak ELM Coil Support in High Nuclear Heat Environment

In Tokomak, the support of the ELM coil, which is close to the plasma and subject to high radiation level, high temperature and high magnetic field, is used to transport and bear the thermal load due to thermal expansion and the alternating electromagnetic force generated by high magnetic field and AC current in the coil. According to the feature of ITER ELM coil, the mechanical performance of rigid and flexible supports under different high nuclear heat levels is studied. Results show that flexible supports have more excellent performance in high nuclear heat condition than rigid supports. Concerning thermal and electromagnetic （EM） loads, optimized results further prove that flexible supports have better mechanical performance than rigid ones. Through these studies, reasonable support design can be provided for the ELM coils or similar coils in Tokamak based on the nuclear heat level.

A history of high-power laser research and development in the United Kingdom

The first demonstration of laser action in ruby was made in 1960 by T.H.Maiman of Hughes Research Laboratories,USA.Many laboratories worldwide began the search for lasers using different materials,operating at different wavelengths.In the UK,academia,industry and the central laboratories took up the challenge from the earliest days to develop these systems for a broad range of applications.This historical review looks at the contribution the UK has made to the advancement of the technology,the development of systems and components and their exploitation over the last 60 years.