热壁加氢反应器现场制造

热壁加氢反应器是现代炼油工业的重大关键设备，利用现场组焊方法生产高质量的热壁加氢反应器属国际领先技术，一重集团公司是国内唯一能够在现场组焊大型热壁加氢反应器的公司，其现场组焊技术在国内处于领先水平，具有国际竞争能力。     

国产热壁加氢反应器制造技术进展

靠自主研究和与国外合作生产，使我公司在八十年代就掌握了２ １２ Ｃｒ－１Ｍｏ 钢热壁加氢反应器的制造工艺技术。此后又不断地进行科技开发与工艺创新，使热壁加氢反应器的制造工艺技术水平与能力大大提高，不仅可满足热壁加氢反应器用户的各种要求，使大型热器加氢反应器的国产化率达８０％ 以上，而且其制造技术水平始终与国外保持同步。     

热壁加氢反应器研制进展

近十几年来,国外逐步用热壁加氢反应器取代冷壁加氢反应器来获得更大经济效益和提高生产安全性。但是,由于垫壁加氢反应器是在高温、高压和临氢条件下操作,技术要求十分严格,目前世界上只有少数几个工业发达的国家能够制造这类热壁加氢反应器。为了加快我国制造热壁加氢反应器的步     

氢扩散对加氢反应器运行的影响

热壁加氢反应器在运行时,氢会渗透进入器壁,当反应器停工时,器壁中溶解氢中的一部分会逸出,而大部分氢仍滞留在器壁之中。这些残留氢使反应器器壁材质脆化,造成反应器发生破坏。从氢扩散的机理及加氢反应器用材具有的特点,分析由于氢扩散造成材质劣化和破坏的原因和预防措施。     

热壁加氢反应器设计和使用的几点探讨

热壁加氢反应器由于长期是在恶劣工作条件下运行,因此对加氢反应器从设计制适使用等方面都提出了较高要求,也是石化设备管理的重点.本文从设计使用两方面,叙述了热壁加氢反应器的设计的基本思想及正确的使用管理方法.     

R401加氢反应器的开罐检验

结合R401热壁加氢精制反应器的开罐检验工作，针对加氢反应器长期运行后产生的影响安全性问题，提出了加氢反应器检验的有关方法和技术要求。通过对加氢反应器随机试块回火脆化量的测定，得到反应器进行35000h后仅有轻微的回火脆化量的结论，提出了加氢反应器安全运行的参考意见。     

加氢反应器装运设计探讨

热壁加氢反应器是大型化工容器,在铁路运输过程中需使用特种车辆并要进行装载加固.本文介绍我公司为抚顺石化总厂制造的热壁加氢反应器的铁路运输用特种车辆的装载加固设计方案.     

大型热壁加氢反应器现场焊后局部热处理技术研究

本文针对大型热壁加氢反应器现场焊后局部热处理技术进行了研究，研究结果为厚壁（≤250mm）加氢反应器在现场组装提供可靠的局部热处理技术和设备。     

在用热壁加氢反应器外壁超声波检测工艺试验和研究

通过对热壁加氢反应器使用过程中容易产生的主要缺陷类型及其常规检验方法的分析 ,对热壁加氢反应器外壁超声波检测工艺进行试验和研究 ,总结出针对产品检测的工艺方法和参数 ,并应用于产品检测中     

大型热壁加氢反应器现场组焊技术

本文较全面地介绍了一重集团公司为实现大型与特大型热壁加氢反应器的现场组焊而在技术、装备、检测手段、质量保证等各方面采取的可行而有效的措施。实践表明，一重集团公司开发出的现场组焊技术完全可以保证在我国内任何地点、任何条件下制造出高质量的国产特大型热壁加氢反应器。     

High-Intensity Neutron Fields for Calibrating the Detectors of a Standard Control System of High-Power Nuclear Reactors

The characteristics of ten high-intensity modelling neutron fields in research nuclear reactors with various ratios of the contributions of thermal and epithermal neutrons have been measured in order to be used for calibrating the internal detectors of the standard control system of high-power nuclear reactors. The neutron fields in the F-1, Gidra, and KVANT reactors are certified as working standards of the first and second kind.     

Asymmetric fission of <Superscript>235</Superscript>U nuclei induced by thermal neutrons and fast neutrons of pulsed nuclear reactors

The contributions that neutrons emitted from the neck of excited dumbbell-shaped fissioning ²³⁵U nuclei at the instant of their fission make to the prompt fission neutron spectrum, as well as the ratios of these contributions, have been measured for nuclear fission induced by thermal neutrons and fast neutrons of pulsed nuclear reactors.     

Suspended heated silicon platform for rapid thermal control of surface reactions with application to carbon nanotube synthesis

Rapid continuous thermal control of chemical reactions such as those for chemical vapor deposition (CVD) growth of nanotubes and nanowires cannot be studied using traditional reactors such as tube furnaces, which have large thermal masses. We present the design, modeling, and verification of a simple, low-cost reactor based on resistive heating of a suspended silicon platform. This system achieves slew rates exceeding 100 degrees C/s, enabling studies of rapid heating and thermal cycling. Moreover, the reaction surface is available for optical monitoring. A first-generation CVD apparatus encapsulates the heated silicon platform inside a sealed quartz tube, and initial experiments demonstrate growth of films of tangled single-wall and aligned multiwall carbon nanotubes using this system. The reactor can be straightforwardly scaled to larger or smaller substrate sizes and may be extended for a wide variety of reactions, for performing in situ reaction diagnostics, for chip-scale growth of nanostructures, and for rapid thermal processing of microelectronic and micromechanical devices.     

Experimental measurements within a phase change metallurgical reactor

The measurement of solidification front evolution is essential for the optimization and control of many important metallurgical processes. However, this measurement is tedious, imprecise, and time consuming. More generally, industry needs reliable instruments for the thermal characterization of phase change reactors. This paper enables researchers with means and instruments to study the thermal behavior of processes involving the transformation of phase change materials up to 1000 °C. In this work, an original experimental setup is described to analyze the behavior of two high temperature phase change materials: zinc and molten salts. In particular, it is possible to evaluate the 2D solid solidification front evolution with time. The measurements done with zinc show the presence of two thermal regimes. A solidification rate of 20 mm h(-1) is measured with two different approaches: thermocouples and a mechanical probe. Finally, an infrared camera is also used to make the link between the external thermal behavior and the solidification front evolution inside the reactor. When implemented within an inverse numerical method, the use of this instrument as a new external sensor looks promising.     

Electric conductance method for the assessment of liquid–gas injection into a large gas–solid fluidized bed

Liquid injections are applied widely in fluidized bed reactors such as Fluid Cokers, fluid catalytic crackers and polymerization reactors. In such industrial processes, it is necessary to optimize the contact between the injected liquid and the bed solids as it has a significant effect on product yields and quality, and reactor operability.     

基于虚拟仪器模糊控制器对化学反应过程温度控制研究

本文叙述基于虚拟仪器技术的模糊控制算法对化学反应器温度的控制,讨论模糊控制器对反应体系的恒温控制和模糊PID对反应过程温度的动态控制。实验表明基于虚拟仪器的模糊控制器对化学反应器温度有很好的控制效果,改善系统的温度控制动态特性和鲁棒性。     

New measurement system for on line in core high-energy neutron flux monitoring in materials testing reactor conditions

Flux monitoring is of great interest for experimental studies in material testing reactors. Nowadays, only the thermal neutron flux can be monitored on line, e.g., using fission chambers or self-powered neutron detectors. In the framework of the Joint Instrumentation Laboratory between SCK-CEN and CEA, we have developed a fast neutron detector system (FNDS) capable of measuring on line the local high-energy neutron flux in fission reactor core and reflector locations. FNDS is based on fission chambers measurements in Campbelling mode. The system consists of two detectors, one detector being mainly sensitive to fast neutrons and the other one to thermal neutrons. On line data processing uses the CEA depletion code DARWIN in order to disentangle fast and thermal neutrons components, taking into account the isotopic evolution of the fissile deposit. The first results of FNDS experimental test in the BR2 reactor are presented in this paper. Several fission chambers have been irradiated up to a fluence of about 7 × 10(20) n∕cm(2). A good agreement (less than 10% discrepancy) was observed between FNDS fast flux estimation and reference flux measurement.     

High-throughput reactor system with individual temperature control for the investigation of monolith catalysts

A high-throughput parallel reactor system has been designed and constructed to improve the reliability of results from large diameter catalysts such as monoliths. The system, which is expandable, consists of eight quartz reactors, 23.5 mm in diameter. The eight reactors were designed with separate K type thermocouples and radiant heaters, allowing for the independent measurement and control of each reactor temperature. This design gives steady state temperature distributions over the eight reactors within 0.5 degrees C of a common setpoint from 50 to 700 degrees C. Analysis of the effluent from these reactors is performed using rapid-scan Fourier transform infrared (FTIR) spectroscopic imaging. The integration of this technique to the reactor system allows a chemically specific, truly parallel analysis of the reactor effluents with a time resolution of approximately 8 s. The capabilities of this system were demonstrated via investigation of catalyst preparation conditions on the direct epoxidation of ethylene, i.e., on the ethylene conversion and the ethylene oxide selectivity. The ethylene, ethylene oxide, and carbon dioxide concentrations were calibrated based on spectra from FTIR imaging using univariate and multivariate chemometric techniques. The results from this analysis showed that the calcination conditions significantly affect the ethylene conversion, with a threefold increase in the conversion when the catalyst was calcined for 3 h versus 12 h at 400 degrees C.     

A Method for Determining the Average Charge inside a Fission Chamber

A procedure for determining the main characteristic of gas-filled ionization chambers, which are intended for neutron flux measurements in reactors, critical assemblies, and other neutron sources, is provided for the first time. The results of an estimation of this characteristic for chambers of various designs are presented. A semiempirical correlation between the design parameters of the fission-chamber and the average charge value appearing in the ionization chamber per one nucleus fission reaction under neutron irradiation is obtained. The method makes it possible to determinate the main characteristic of gas-filled fission chambers and their maximum sensitivity to thermal neutrons to an error of no more than 7 and 10%, respectively.     

低温等离子体处理柴油机有害排放的比较研究

分析了低温等离子体转化柴油机排气中有害成分的反应机理,设计了三种不同结构类型的低温等离子体反应器,并进行了基于发动机台架的实验研究。研究结果表明,低温等离子体对柴油机排气中的颗粒物及NO有较好的转化作用,采用全流式低温等离子反应器,延长排气在反应器中的滞留时间,有利于提高能量利用率及排气中颗粒物、NO的分解转化率。