共查询到20条相似文献,搜索用时 15 毫秒
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作为国际热核聚变实验堆(ITER)的重要部件之一,屏蔽包层承受高强度聚变中子辐照,需要定期更换和维修。当活化的屏蔽包层从ITER托卡马克装置移到热室时,可能会给工作人员造成严重的辐射照射,是ITER大厅和热室屏蔽设计的重要辐射源。文中基于ITER最新中子学分析基准模型和"二步法"停堆剂量计算方法,使用超级蒙特卡罗核计算仿真软件系统SuperMC针对15号屏蔽包层建立精细的中子学模型,并计算分析包层的活化情况及最严重情况下的周围辐射剂量率,并初步应用于ITER赤道窗口室的屏蔽分析。计算结果显示,单个包层周围最大剂量率为350 Sv/hr,当传送小车停留在赤道窗口室内时,窗口室屏蔽门外剂量率高于10 mSv/hr,不足以满足设计要求。 相似文献
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M. Angelone P. Batistoni F. Moro M. Pillon R. Villari M. Laubenstein M. Loughlin 《Fusion Engineering and Design》2012,87(5-6):910-915
A mock-up of ITER including the inboard shield, the vacuum vessel and the coil region, was set up at ENEA Frascati and irradiated with 14 MeV neutrons produced by the Frascati Neutron Generator (FNG). The mock-up dimensions and materials composition are consistent with the current ITER design.The primary objective of the experiment was to validate the MCNP calculations (C) of nuclear heating measured (E) in the region corresponding to the ITER Toroidal Field (TF) coil. An accuracy on C/E ratio ≤±10% was required.The neutronics and shielding properties of the mock-up were also studied throughout the measurement of selected activation reaction rates up to about 1 m depth. Due to the very low activity induced in the foils, the measurements in the deepest experimental positions were performed at the underground low background facility of the Laboratori Nazionali del Gran Sasso, using ultra-low background high purity germanium (HPGe) detectors.The measured reaction rates and nuclear heating were thus compared with the results of the Monte Carlo code MCNP5 coupled with the FENDL-2.1 library. 相似文献
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S. Simrock L. Bertalot M. Cheon C. Hansalia D. Joonekindt G. Jablonski Y. Kawano W.-D. Klotz T. Kondoh T. Kozak P. Makijarvi D. Makowski A. Napieralski M. Orlikowski M. Park S. Petrov A. Piotrowski P. Predki I. Yonekawa 《Fusion Engineering and Design》2012,87(12):2100-2105
ITER project's long time span and the nature of the instrumentation and control (I&C) procurement procedures for the Plant Systems require that the ITER Organization defines and follows well recognized standards which are used both by the industry and in physics experiments. The ITER I&C standards are defined in the Plant Control Design Handbook (PCDH) [1]. The ITER Organization has selected PCI Express and Ethernet for IO intercommunication to be used for plant system instrumentation for fast controllers. The decision on the usage of serialized I/O bus protocols is based on the impressive performance and the commercial availability. The form factors that will be supported by CODAC include PXIe, MicroTCA, and AdvancedTCA platforms. While the PXIe form factor is already well established for instrumentation purposes through the PXI Systems Alliance (www.pxisa.org), the AdvancedTCA and MicroTCA platforms which were originally targeted for the telecommunications market (www.picmg.org) are currently optimized and specified for instrumentation use through the xTCA extensions for physics [2]. The objective of this study is the evaluation of an integrated ATCA controller design using only commercial components. 相似文献
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In the ITER edge Thomson scattering measurement system, polychromators with optical band-pass filters and avalanche photodiodes are planned to be used. In this paper, we optimized the transmission wavelength ranges of the optical filters by a numerical method. Since measurements in a high electron temperature range are required for the measurement system, the Thomson spectrum could overlap a strong line emission of Dα when the electron temperature is rather high. It is shown that a filter whose transmission wavelength range is shorter than Dα becomes important to decrease the measurement error in the high temperature range. Moreover, it is found that a filter whose transmission wavelength range is above 1064 nm (laser wavelength) is useful to improve the measurement accuracy, in particular, when the number of filters is more than six. 相似文献
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Lawrence Jones Jean François Arbogast Angel Bayon Aldo Bianchi Joan Caixas Aldo Facca Gianbattista Fachin José Fernández Benoit Giraud Marcello Losasso Thorsten Löwer Gonzalo Micó Jose Miguel Pacheco Roberto Paoletti Gian Paolo Sanguinetti Vassilis Stamos Massimiliano Tacconelli Alexandru Trentea Yuri Utin 《Fusion Engineering and Design》2012,87(5-6):700-705
The contract for the seven European Sectors of the ITER Vacuum Vessel, which has very tight tolerances and high density of welding, was placed at the end of 2010 with AMW, a consortium of three companies. The start-up of the engineering, including R&D, design and analysis activities of this large and complex contract, one of the largest placed by F4E, the European Domestic Agency for ITER, is described. The statutory and regulatory requirements of ITER Organization and the French Nuclear Safety regulations have made the design development subject to rigorous controls. AMW was able to make use of the previous extensive R&D and prototype work carried out during the past 9 years, especially in relation to advanced welding and inspection techniques. The paper describes the manufacturing methodology with the focus on controlling distortion with predictions by analysis, avoiding use of welded-on jigs, and making use of low heat input narrow-gap welding with electron beam welding as far as possible and narrow-gap TIG when not. Further R&D and more than ten significant mock-ups are described. All these preparations will help to assure the successful manufacture of this critical path item of ITER. 相似文献
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F. Crisanti A. Cucchiaro R. Albanese G. Artaserse M. Baruzzo T. Bolzonella G. Brolatti G. Calabrò F. Crescenzi R. Coletti P. Costa A. della Corte A. Di Zenobio P. Frosi D. Harting L. Lauro Taroni G. Maddaluno D. Marcuzzi F. Maviglia L. Muzzi S. Wiesen 《Fusion Engineering and Design》2011,86(6-8):497-503
Fusion Advanced Studies Torus (FAST) aims to contribute to the exploitation of ITER and to explore innovative DEMO technology. FAST has been designed to study, in an integrated scenario: (a) relevant plasma-wall interaction problems, with a large power load (P/R ~ 22 MW/m; P/R2 ~ 12 MW/m2) and with a full metallic wall; (b) to tackle operational problems in regimes with relevant fusion parameters; (c) to investigate the non-linear dynamics of fast particles (alpha like) in burning plasmas. FAST will operate on a wide parameters range, namely in high performance H-mode (BT ~ 8.5 T; IP ~ 8 MA) as well as in advanced Tokamak operation up to full non-inductive current scenario (IP ~ 2 MA). The main heating is based on 30 MW ICRH, but the ports have been designed to allocate up to 20 MW of 1 MeV NNBI. Helium gas at 30 K is used for cooling of the full machine, a preliminary analysis shows the possibility of realizing FAST with a complete superconductor set of coils. An innovative active system is under development to reduce and to control the magnetic ripple. Tungsten (W) or liquid lithium (L–Li) has been chosen for the divertor material plates and the code EDGE2D has been used to optimize the divertor geometry. 相似文献
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H.J. Liu Y. WuZh. B. Ren Y. ShiJ.L. Chen F. LongM. Yu L. Qian 《Fusion Engineering and Design》2011,86(12):2827-2830
A new facility had been set up to test the low temperature properties of the short sample of the small-size cable-in-conduit conductor (CICC). The facility consisted of the background magnet which could provide 7 T centric magnetic field, a 50 kA superconducting transformer which provided sample current, a 500 W/4.5 K helium refrigerator which produced both the liquid helium (LHe) and supercritical helium (SHe). An ITER CC conductor short sample was prepared and measured in this testing system. Tcs of 7.02 K (@4.1 T, 10 kA) and Ic of 8.9 kA (@4.1 T, 7.06 K) were measured. 相似文献
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氡子体α能谱法测量仪器探测效率的测定 总被引:1,自引:0,他引:1
在氡子体α能谱法测量中,一个需要考虑的问题是探测器对不同能量的α粒子是否具有相同的探测效率。本文用^241Am标准源和加拿大Pylon公司的氡子体标准源对ORTEC八通道α谱仪进行了全谱和高、低能量段探测效率的测定,并对两种测量方法存在的误差进行了分析。测量结果表明,两种方法测得全谱探测效率在误差范围内是一致的;在用氡子体源测量谱仪的探测效率时,α能谱由于滤膜的自吸收而存在着峰重叠现象,经重叠因子修正后,仪器对氡子体较高能量的α粒子(7.69 MeV)的探测效率要略大于较低能量的α粒子(6.00 MeV),且探测效率的差异随滤膜种类的不同而变化。用氡子体标准源对仪器进行刻度更接近于氡子体测量的实际情况。 相似文献
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使用中子学程序系统VisualBUS和活化数据库EAF-99对DFLL-TBM的高级子模块DLL-TBM的活化特性进行了计算和分析,包括DLL-TBM各部件在不同停堆时间的活度、衰变余热和剂量率.活化计算所需要的三维中子能谱通过MCNP/4C中子/光子输运程序和国际原子能机构发布的FEND1.0数据库计算得到.在活化计算分析的基础上,参照欧洲聚变堆安全和环境评估(SEAFP)策略中有关核废料的处理标准评估了TBM各区材料在退役后的废料处理工作,包括核废料应该采用何种适当的方式进行处理及其被完全清除干净的可行性. 相似文献
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Marcello Losasso Maria Ortiz de Zuniga Lawrence Jones Angel Bayon Jean-François Arbogast Joan Caixas José Fernández Stefano Galvan Teresa Jover Kimihiro Ioki Michal Lewczanin Gonzalo Micó Jose Miguel Pacheco Joseph Preble Vassilis Stamos Alexandru Trentea 《Fusion Engineering and Design》2012,87(5-6):427-431
The contract for the seven European Sectors of the ITER Vacuum Vessel (VV) was placed at the end of 2010 with a consortium of three Italian companies. The task of placing and the initial take-off of this large and complex contract, one of the largest placed by F4E, the European Domestic Agency for ITER, is described. A stringent quality controlled system with a bespoke Vacuum Vessel Project Lifecycle Management system to control the information flow, based on ENOVIA SmarTeam, was developed to handle the storage and approval of Documentation including links to the F4E Vacuum Vessel system and ITER International Organization System interfaces. The VV Sector design and manufacturing schedule is based on Primavera software, which is cost loaded thus allowing F4E to carry out performance measurement with respect to its payments and commitments. This schedule is then integrated into the overall Vacuum Vessel schedule, which includes ancillary activities such as instruments, preliminary design and analysis. The VV Sector Risk Management included three separate risk analyses from F4E and the bidders, utilizing two different methodologies. These efforts will lead to an efficient and effective implementation of this contract, vital to the success of the ITER machine, since the Vacuum Vessel is the biggest single work package of Europe's contribution to ITER and is the largest component of the ITER device. 相似文献
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《等离子体科学和技术》2020,22(8):84004
The time-of-flight enhanced diagnostics(TOFED) neutron spectrometer has been installed in TOFED house, which is a newly-built neutron diagnostic lab outside the EAST experimental hall. The line of sight(LOS) of TOFED is defined by the collimator going through the 150 cm biological shielding wall, which can reduce background neutrons very effectively for the neutron spectral measurements. The Monte Carlo code MCNP5 is used in the simulations to characterize collimation effects and the radiation safety of the new house. The collimator makes neutron flux almost fully perpendicular to S1 detectors. In addition, the proportion of scattered neutrons in the LOS of the TOFED is obtained for the measured spectral data interpretation. The simulation results show that the TOFED house satisfies the requirement for the TOFED operations at EAST and gives a safe environment for personnel access during the EAST operation. 相似文献
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Jianqiang HU Ahdi LIU Chu ZHOU Xiaohui ZHANG Mingyuan WANG Jin ZHANG Xi FENG Hong LI Jinlin XIE Wandong LIU Changxuan YU 《等离子体科学和技术》2017,19(8):84002
A new integrated technique for fast and accurate measurement of the quasi-optics,especially for the microwave/millimeter wave diagnostic systems of fusion plasma,has been developed.Using the LabVIEW-based comprehensive scanning system,we can realize not only automatic but also fast and accurate measurement,which will help to eliminate the effects of temperature drift and standing wave/multi-reflection.With the Matlab-based asymmetric two-dimensional Gaussian fitting method,all the desired parameters of the microwave beam can be obtained.This technique can be used in the design and testing of microwave diagnostic systems such as reflectometers and the electron cyclotron emission imaging diagnostic systems of the Experimental Advanced Superconducting Tokamak. 相似文献