模块式套管型随堆辐照考验装置的研制

为进行材料在高γ释热区的辐照考验,研制了模块式套管型随堆辐照考验装置(MTIR)。该随堆辐照考验装置具有辐照温度测量和调节功能,在高γ释热率条件下能够对试验段进行强化冷却。堆内验证试验表明,该装置能够实现材料样品的辐照考验指标,可使高通量工程试验堆(HFETR)内层辐照孔道得到有效利用,缩短材料堆内辐照试验周期,提高HFETR辐照能力。     

日本原子能研究所用改进型堆芯运行JMTR堆

【《日本原子》2002年1月刊报道】 2001年11月20日，日本原子能研究所（JAERI）在其所属的大洗研究单位利用新的改进型堆芯开始日本材料试验堆（JMTR）的第142次运行循环，这个循环于2001年12月15日结束。 JMTR已广泛地用于中子辐照试验，以确定反应堆材料和燃料的行为和特性。然而，最近对高度一体化中子辐照的需求与日俱增，该研究所设法增加JMTR的年运行天数。 在燃料更有效燃烧的改进型堆芯中，在此循环期间装载了29个燃料组件，取代了原先的27个。燃料元件在每次运行循环中位置轮换，而且每个循环只更换几个燃料组件，因此每个…     

日本原研改良材料试验堆

【日本《原子能视野》2002年6月刊报道】 2002年4月8日,日本原子能研究所宣布为了正确测定轻水堆内管道等的辐照应力腐蚀开裂(IASCC),已对大洗研究所的材料试验堆(JMTR)进行了改造。轻水堆经过长时间运行后,堆内管道及构件处于中子照射及高温高压水形成的恶劣环境下,可能会因IASCC而酿成事故。为了消除这个隐患,已对JMTR进行改进,使其能够事前准确地捕捉到有关IASCC的信息。日本原研改良材料试验堆     

CARR铱源试验靶件设计和试验验证

为配合中国先进研究堆(CARR)铱源辐照生产项目,设计制造了铱源试验靶件,对试验靶件的设计参数、结构尺寸进行了介绍。在堆外使用专门的传热装置模拟铱源靶件的外部和内部传热工况,测量了用于模拟辐照罐壁面温度和样品温度的传热装置的壁面温度和内部温度,结果验证了热工分析方法是合适的。入堆试验靶件由含有铱片样品的辐照罐和等量发热的模拟罐组成。堆内试验获得的数据综合验证了试验靶件物理热工的分析结果,这个结果可对CARR铱源辐照生产安全评审提供依据且偏于安全。     

余热排出系统中的热管设计及传热性能研究

本文建立了单根热管的优化设计流程及其传热传质数学物理模型,考虑热管的工作环境,对用于核反应堆非能动余热排出系统中热管换热器的热管进行了完整的优化设计和传热特性分析。分析表明：复合型吸液芯热管满足余热排出系统的传热需求,其传热功率主要受热管毛细极限、沸腾极限及总热阻的影响。相同吸液芯厚度下,复合型吸液芯热管的毛细极限较单一丝网吸液芯热管的毛细极限提高100%～700%。改变热管的外径或吸液芯厚度,即蒸气腔直径减小,沸腾极限明显减小。当单根热管传热功率大于1 kW时,热管各段长度分别为0.4、0.2、0.4 m,外径为30 mm,吸液芯是厚度为2 mm的400目+50目复合型丝网结构。本文为高性能的热管换热器设计及传热特性分析提供了理论支撑。     

TOPAZ-Ⅱ改进型热管辐射换热器传热单元数值研究

针对前苏联研制的TOPAZ-Ⅱ空间热离子反应堆,结合成熟的高温热管技术,对改进型热辐射换热器传热单元进行瞬态特性研究。采用有限元方法对热管瞬态启动特性进行数值模拟。翅片温度计算采用有限差分进行求解,并与热管壁面进行单向耦合传热。热管启动过程中采用Cotter热管极限理论,即重力极限、声速极限、携带极限来判定热管启动状态。研究结果表明：热管390 s内启动迅速,在启动第2阶段遇到声速极限,从而限制了热管启动时间。热管和翅片最终达到稳态,温度分布均匀,当量换热系数为1783.25 W/m²。热管换热单元能有效地将热量导入到外界。     

用于HFETR的材料辐照试验的新型装置

针对各种反应堆结构材料辐照样品的温度与中子注量要求，设计了一种适用于在高通量工程试验堆(HFETR)堆内进行材料辐照试验的新型辐照装置。本文简要介绍了该装置的结构特点、技术特点、辐照罐的设计以及测试系统与试验情况。目前，该装置已完成了多种材料的辐照试验，结果表明：装置具有温度调节范围宽(0-120℃)、系统调节能力强、安全可靠和出入反应堆方便等优点．完全能满足各种反应堆结构材料的高低温辐照试验要求。     

中国实验快堆结构材料辐照装置设计

为在中国实验快堆(CEFR)上开展国产快堆包壳材料的辐照试验,进行了CEFR首个结构材料辐照装置的设计。材料辐照装置的创新设计基于CEFR的辐照条件和堆芯组件的基本结构,通过在辐照装置内部设置不同气隙尺寸的辐照罐,实现了在快堆不同功率稳态运行条件下(40%和100%额定功率)对材料样品不同辐照温度(450~600℃)的要求。辐照装置具有样品辐照温度与中子注量率的非在线监测功能,其结构具有通用性,能满足材料辐照标准试样最大装载的需要。通过对辐照装置进行热工分析和堆外的传热验证试验、流阻特性和结构稳定性验证试验,保证了辐照装置的设计能满足材料辐照任务的要求。     

干道式高温热管的传热性能试验研究

干道式高温热管传热性能试验主要是为了获得干道式热管在不同温度范围的传热极限及重力场对传热极限的影响。在真空条件下启动热管,调节水套气隙氩气和氦气比例来测量声速极限,建立可调角度台架得到不同倾角下热管的极限传热性能。试验得到400～650 ℃工作温度下热管的极限传热功率曲线及不同倾角下热管的极限传热功率。此类热管510 ℃以下传热极限为声速限;±10°范围内重力对传热极限无影响;极限传热功率为2.8 kW。     

CFETR先进小样品辐照胶囊优化与热工安全分析

中国聚变工程试验堆（CFETR）先进材料辐照考验样品所在胶囊结构较为复杂,其内部填充氦气,胶囊肋条尺寸、位置以及胶囊内部填充材料对样品温度影响大。基于STAR-CCM+程序建立CFETR先进小样品辐照装置内胶囊全尺寸模型,针对样品的目标温度,对胶囊的肋条和填充材料进行了调整。对于胶囊内整体样品释热率较低的情况,采用释热率较大的钨材料作为填充材料,可以明显提高整体样品温度;对于局部样品释热率差别较大的情况,调整局部肋条的尺寸和位置,能够很好控制样品间的温度,使样品计算温度满足目标温度范围。结果表明：采用上述方法进行优化后,样品中心温度能够满足目标温度范围,且满足入高通量工程试验堆（HFETR）辐照的热工安全,保证整个辐照任务能够顺利开展。     

热管在核电工程中的应用

概述了热管在空间核电源、核废料冷却，事故条件下安全壳的保护等方面的应用情况，并提出了将热管应用于核电工程中的蒸汽发生器。介绍了国内外针对这些应用所进行的开发研究工作。已有的研究工作表明：根据不同的温度范围选择适当的热管壳体材料、工作介质和吸液芯结构，经过仔细的设计，必要的实验和精良的制作，热管性能可以满足核电工程技术要求并能达到实用化程度。     

Performance evaluation of ultra-long lithium heat pipe using an improved lumped parameter model

Lithium heat pipes have broad applications in heat pipe cooling reactors and hypersonic vehicles owing to their ultra-high working temperature.In particular,when the length of the lithium heat pipe is ultra-long,the flow and heat transfer characteristics are more complex.In this study,an improved lumped parameter model that considers the Marangoni effect,bending effect,and different vapor flow patterns and Mach numbers was developed.There-after,the proposed model was verified using the University of New Mexico's Heat Pipe and HTPIPE models.Finally,the verified model was applied to simulate the steady-state operation of an ultra-long lithium heat pipe in a Heat Pipe-Segmented Thermoelectric Module Converters space reactor.Based on the results:(1)Vapor thermal resistance was dominant at low heating power and decreased with increasing heating power.The vapor flow inside the heat pipe developed from the laminar to the turbulent phase,whereas the liquid phase in the heat pipe was always laminar.(2)The vapor pressure drop caused by bending was approximately 22-23％of the total,and the bending effect on the liquid pressure drop could be ignored.(3)The Marangoni effect reduced the capillary limit by hindering the liquid reflux,especially at low vapor temperatures.Without considering the Marangoni effect,the capillary limit of the lithium heat pipe was overestimated by 9％when the vapor temperature was 1400 K.(4)The total thermal resistance of the heat pipe significantly increased with increasing adiabatic length when the vapor tempera-ture was low.Further,the wick dryness increased with increasing adiabatic length at any vapor temperature.Such findings improve on current knowledge for the optimal design and safety analysis of a heat pipe reactor,which adopts ultra-long lithium heat pipes.     

密度锁内分层传热特性的初步探讨

通过可视化观察方法,对3种不同实验管内的流体分层传热特性进行实验研究,同时,建立传热计算模型,对密度锁内的传热机理进行分析.结果表明:密度锁内的分层工质自上而下分为:混合层、界面层、导热层.混合层内的传热以对流为主,其余两部分的传热以导热为主.对不同管径的研究表明,密度锁内的蜂窝通道能有效地抑制扰动作用,减小混合层的厚度,降低通过密度锁的热量传递.     

Feasibility study on cryogenic irradiation facility in JMTR

The Japan Materials Testing Reactor (JMTR) of the Japan Atomic Energy Agency is a testing reactor with first criticality in March 1968. The reactor has been utilized for various neutron irradiation tests on nuclear fuels and materials, as well as for radioisotope production. The operation of JMTR stopped temporarily in August 2006 for refurbishment and improvement. The renewed JMTR will resume operation in Japanese fiscal year 2011. For the resumption of the new JMTR, the new irradiation facilities, the usability improvements, the target, and the expected roles of the new JMTR have been discussed. As one of the new irradiation facilities, the cryogenic irradiation facility, which is used for the investigation on the low-temperature irradiation behavior of materials such as superconducting magnet materials for fusion reactors, has been desired. In this study, the feasibility of low-temperature irradiation tests with the cryogenic irradiation facility was investigated, and the conceptual design of the facility was carried out. As a result, it was found that irradiation tests at temperatures below 20 K for the development of the superconducting magnet materials can be realized by the installation of an irradiation capsule into an irradiation hole with low γ heating and by the adoption of vacuum jacketed tubes to connect between the capsule and a cooling system.     

不凝性气体对高温锂热管传热特性的影响研究

热管作为一种具有高热导率的传热装置,工作核心在于其内部工作流体的蒸发和冷凝。若热管工作过程中气腔内存在不凝性气体,主流区中蒸气和不凝性气体在对流运动的作用下将一起移动到气-液分界面,不凝性气体的存在阻碍了工作流体在气-液交界面处的正常冷凝。本文基于热阻网络法添加了不凝性气体区域传热模型,研究了不凝性气体对高温锂热管稳态传热特性的影响。结果表明,热管达到稳态时不凝性气体的存在缩短了热管的有效传热长度,破坏了热管的等温性和良好的传热效率。此外随着不凝性气体体积份额的增大,不凝性气体区域温度降低幅度越大;随着热管蒸发段输入功率的增大,热管正常工作区域整体温度越高,相同质量的不凝性气体占据的体积份额越小,热管壁面温度出现明显温度梯度降低的位置随着功率升高而向下游移动。     

窄缝矩形通道单相流动及传热实验研究

以垂直向上窄缝矩形通道内去离子水为流动介质,对单相等温流动及恒热流密度条件下的单相传热进行了实验研究.结果表明,窄缝矩形通道内的单相等温流动特性及单相传热特性并未偏离常规尺度通道内的相关规律,采用经典理论解或关系式能获得较好的预测结果.     

基于简单开式布雷顿循环的热管反应堆系统功率质量比影响因素初步探索

基于简单开式布雷顿循环的热管反应堆系统具有结构简单、固有安全、放射性泄漏风险低等特点,是小型可移动反应堆的潜在优势技术选项,其功率质量比是评价总体方案先进性的重要指标。本文以5MW热管反应堆为研究对象,建立包含热管反应堆与开式布雷顿发电装置的方案功率质量比评估模型,对多种关键参数对总体指标的影响规律进行了探索。研究表明功率质量比随热传导途径上温差增大而先提高后降低,最优值则与堆芯基体最高温度限值正相关。在给定温度限值条件下,热管反应堆电源系统内热量传输途径上温差设计是热管反应堆优化设计的关键因素。未来可进一步细化模型,对压气机、涡轮、热管等进行更详细建模,提高模型准确程度。     

热管技术及性能分析程序研究

作为一种高效的热传输手段，热管具备可靠性高、传热温差小、无需外力驱动等特点，因此在航天航空、核工程等领域得到广泛研究和应用。为更好地应用热管技术开展新型反应堆的设计和研发，掌握热管性能分析的理论方法和软件工具，本文开展了热管技术及相关程序的开发。对热管的结构和工作原理、种类、工作特性等进行了分析，研究了热管分析的基本理论和各种传热极限的计算模型。在此基础上开发了热管性能分析程序HEPAC，其具备各类热管的传热特性分析及传热极限计算能力，通过与相关实验数据的对比分析，验证了程序的正确性。相关程序开发为各种热管式反应堆的设计分析提供了重要工具。     

Space reactor power systems with no single point failures

Nuclear reactor power systems could revolutionize space exploration and support human outpost on the moon and Mars. This paper reviews various energy conversion technologies for use in space reactor power systems and provides estimates of the system's net efficiency and specific power, and the specific area of the radiator. The suitable combinations of the energy conversion technologies and the nuclear reactors, classified based on the coolant type and cooling method, for best system performance and highest specific power, are also discussed. In addition, a number of power system concepts with both static and dynamic energy conversion, but with no single point failures in reactor cooling, energy conversion and heat rejection, and for nominal electrical powers up to 110 kW_e, are presented. The first two power systems employ reactors cooled with lithium and sodium heat pipes, SiGe thermoelectric (TE) and alkali-metal thermal-to-electric conversion (AMTEC), and potassium heat pipes radiators. The reactors heat pipes operate at a fraction of the prevailing capillary or sonic limit, and in the case of a multiple heat pipes failure, those in the adjacent modules remove the additional heat load, thus maintaining the reactor adequately cooled and the power system operating at a reduced power. The third power system employs SiGe TE converters and a liquid metal cooled reactor with a divided core into six sectors that are neurotically and thermally coupled, but hydraulically decoupled. Each sector has a separate energy conversion loop, a heat rejection loop, and a rubidium heat pipes radiator panel. When a core sector experiences a loss-of-coolant, the fission power of the reactor is reduced, and that generated in the sector in question is removed by the circulating coolant in the adjacent sectors. The fourth power system employs a gas cooled reactor with a core divided into three identical sectors, and each sector is coupled to a separate Closed Brayton Cycle (CBC) loop with He-Xe binary mixture (40 g/mol) working fluid, a secondary loop with circulating liquid Nak-78, and two water heat pipes radiator panels.     

Experimental study on the sub-atmospheric loop heat pipe passive cooling system for spent fuel pool

As one kind of the natural circulation cooling system, loop heat pipe is promising in improving the safety of the nuclear power station since it is passive and has no electricity driven components. A novel heat pipe cooling system is designed for passively removing the residual heat released by the spent fuel stored in the spent fuel pool (SFP) under the accidental conditions such as the station blackout. This system is characterized by its large-diameter and long-length evaporator. Its working fluid is water and it's sub-atmospheric. To test such system's heat transfer performance and get to know its thermo-fluid dynamics, a test facility for a simplified heat pipe made of one evaporator tube and one condenser has been developed. The heat transfer rate of the simplified heat pipe is obtained in a wide range of conditions covering the potential working conditions in spent fuel pool. Moreover, it's found that heat pipe with such a large-diameter and long-length evaporator is vulnerable to be unstable. The periodic state mode is more likely to happen when the heat source temperature, the air velocity or the volumetric filling ratio is low. Furthermore, the effects of hot water temperature, the air velocity and the filling ratio of the water in the circulation system have been analyzed.